ML20126J580
| ML20126J580 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/21/1992 |
| From: | Hogge A DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20126J571 | List: |
| References | |
| NUDOCS 9301060213 | |
| Download: ML20126J580 (226) | |
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~(m 221 Pages FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. o ,, Duke Power Co. 422 S. Church St., Charlotte. NC 28201 (Name and Address of Owcer) 2 pi,,, Catawba Nuclear Station, 4800 Concord Road, York, SC 29745 (Name and Address of Plant)
- 3. Plant Unit 1 4, owner Ceruficate of Authornanon (if required) NA
- 5. CommercialSernce Dste 6/29/85 6. Natnonal Board Number for Unit 130
- 7. Components laspected Manufactwve Component of Manufacturer or installer $ tate or National Appurtenance or Installer Seral No. Pronnce No. Board No, 5EE SECTION 1 PARAGRAPH 1.5 IN THE ATTACHED REPORT _
Notei Supplemental sheets in f orm of lists, sketches, or drawings may be used prowded (1) size is 8 % in. x 11 in,. (2) information in items 1 through 6 on this data report is tncluded on each sheet, and (3) each sheet is numbered and the number of snects is recorded at the top of this form. f
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_ ____.___ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i . ii.
s FORM NIS 1 (back)
- 8. Examinanon Dat,,06/09/91 to10/15/92 9 inspecooo ini,,,,3 f,, 06/29/8(06/29/95 _
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work requind for cumni inierval. See Attached Report
- 11. Abstract of Conditione Noted- See Attached Report iz. Adsnaa of Comam unmins necommadet and Taka See Attached Report we ecrafy that the statements tr.ade in this report an comet and the examinations and corrective men.
sures taken conform to the rules of the ASME Code, Section XI. G Date }T Z( 1p Signed Duke Power Co. Owner 37 hf@ _ Cernficate of Authorization No. (if applicable) NA g ,pi,,,to , p.,, NA , CERTIFICATE OF INSERVICE INSPECTION 1 the underugned, holding a valid commw' a'on issued y the National Board of Boilet and Pressun Vesel Inspectoys an4/or State or Provsace of N. Carol na and employed byThe HSBI&l Co.
- of HartTord, have inspected the components desenbed la this Owners' Data Report during the pen'od to . and state that to the sest of my knowledge and belief, the Owner has performed examinanons and taken correctrve nwasures desenbed la this Owners' Data Report in accordance with the requirements of the ASME Code,$ection XI.
By signing this cernficate neither the Inspector not his employer makes any warranry, expressed or implied, concermag die examinations and concedve mesmares desenbed in this Owners' Data Repon. Furthermore, neither the inspector nor his employer shall be liable in any rnanner for any personal injury or property damage of a low of any kind ansing from of connected with this inspection.
^
bgerowdd v, Inspector's Signature Comm_o,s utAM Nauonal Board, State, Provmce and No. 4%
- The Hartford Steam Boiler Inspection & Insurance Co.
200 Ashford Center North Suite 300 Atlanta, GA 30338 s
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s 5 o gyg-INSERVICE INSPECTION REPORT 4 . UNIT .1 CATAWBA 1992 REFUELING OUTAGE 6-P Location: - 4800 Concord Road, York, SC 29745 3
~ NATIONAL BOARD NO. 130 COMMERCIAL SERVICE DATE: JUNE 29, 1985 i
i ! L Owner: Duke Power Company F 422 S. Church St. Charlotte, NC 28201 + i- t e h i ' Revision 0
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p , l , L Prepared By: . 4/ / Date -MM M
.. Reviewed By: _. m Date $ b NI
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TABLE.0F CONTENTS:
.SectionE Title Revision.
1, Summary of. inservice Inspection 0-
- 2. Status of Required Inspections- 0'
- 3. . Final Inservice Inspection Plan-for= Outage 6 0'
- 4. Results'of-Inspections Performed ~During Outage _6 0 l
, 5. Class 1 Inspection Results 0 _j
- 6. Class 2 Inspection Results -0
- 7. Augmented. Inspection Results 0 l'
- 8. - Per sonnel Equipment, and Material Certifications _0
-9. Problem Investigation Reports . 0 ;-
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- 10. Reference Documents 0-( . ,
- 11. . Class 1 and-2 Repairs and Replacements 0
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'10 . Summarv 'of Inservice Inspe_cijan.
This report describes the Inservice Inspection'of Duke Power:
~
l Company,'s Catawba Nuclear Station Unit I during the 1992: Refueling Outage:(also referred to as Outage' 6, which..is in the -Thit dt Inspection Period of-the First inspection Interval). -
= +
included in this report are the final-Inservice Inspection Plan,-- the inspection results for each item, a summary for each category 1 of examination and corrective action'taken when unacceptable . conditions were found. In addition,- there_is a section included for repairs and replacements required since June 9 1991. 1.1 Class 1 Inspection The Class 1 Inservice Inspection included examinations on the . Reactor Vessel CRD. Housing Welds, Steam Generator 1A Channel Head to Tubesheet Weld and on Pressurizer Safety Nozzle To Safe End Butt Welds. Examinations were performed on Class 1 Dissimilar - Metal Butt Welds of the Upper Head Injection System,.and on circumferential butt welds i_n the Reactor Coolant _(NC),-and Safety- _ Injection (NI) Systems. Also, examinations were performed on Reactor Coolant Pump IC Main Flange Bolting and INC-27 Valve Body Weld. Visual examinat_lons were performed on the Class 1 Pressure
-(h d
Boundary during System Leakage Tests. Reactor Coolant Pumps 1A,. 1B, 1C and 10 Flange, Reactor Coolant Pump IC Seal Gland--and Seal Housing Bolts, Valves INC-1, INC-2 and 1NC-3 Studs and Nuts-and the interna 1' surfaces of Valves INC-27 and 1NI-29 also were examined. In addition, visual-examinations were performed on Class.1 Component Supports of Reactor . Coolant (NC), Residual Heat , Removal (ND), Safety-Injection (NI) Systems and-on pressurizer; . Support Skirt, Support Lugs, Upper Support and Lower Support Frame. The Inconel 600 tubing in Steam Generators 1A.-18, 1C and 10 was inspected by eddy current during Outage 6'. -The results are shown-in the Catawba Unit 1 July 1992 Refueling Outage Eddy Current-Examination Report. - Reportable indications were found on-the Class 1 Inspections shown in this section. Inspection and evaluation data for each reportabl_e indication is found in the-Catawba. Unit 1 July 1992 Refueling Outage Eddy Current Examination Report. A-detailed description of each inspection is found'in the= final Inservice Inspection Plan'.in;Section 3-of this report. Results of each examination are.found in Section 4. s( EQA408- Page 1 - Revision 0 December.9, 1992-t- 'ev- y . + yen -+ -%-e. r' r b . - h .. yy . . , g- y- - c , v +
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-1 '. 2 Class 2'In a cM ga?
1j7 The Class"2' Inspections' included examinations on RHR Heat Exchanget 1A Inlet Nozzle "A," and Outlet Nozzle "B" Nozzle to: Shell Welds,- Steam Generator IB-Main-Steam Nozzle to Upper llead z Weld and Steam Generator-10 Auxiliary; Feedwater Nozzle to:Shell l Weld. Examin'ations. were performed on_circumferential butt welds. c' of the Auxiliary Feedwater (CA), Main Steam Supply- to Auxiliaty Equipment (SA), Main Steam (SM).and Main Steam Vent _t'o Atmosphere i
, (SV), Main Feedwater (CF)-and Safety-Injection (NI)- Systems. 3 Examinations were-performed on-piping integrally-welded attachments- of Main' Feedwater .(CF) System.
Visual examinations were performed on the Class 2 Pressure Boundary during System Functional Tests. Also, visual examinations were performed on Class 2 Component Supports of. Auxiliary Feedwater (CA), Main Feedwater (CF), Rtfueling Water (FW), Safety Injection (NI), Main Steam Supply to Auxiliary Equipment (SA) and Main Steam-(SM) Systems. A detailed description of each inspection is found in the final-Inservice-Inspection Plan in Section 3 of.this report. Results-of- ' each examination are found in Section 4. 1.3 Augmented Inspec1193 j .- T Augmented Inspections at Catawba 1 consisted of Reactor-CoolantD Pump Flywheel examinations, Steam Generator Tubing examinations, Pipe Rupture Protection examinations,'and Thermal Stress; Piping-examinations.- A detailed description of 'each examination is-found. in the final Inservice Inspection Plan in Section.3 of this report. Results of each examination are found in Section 4. 1.4 Alternate Inspection No-alternate examinations were performed during Outage 6. . 1.5 .1dentification-Numbers-Owner: Duke Power Company, 422 S. ' Church Street, Charlotte, NC 2820l? Plant: Catawba. Nuclear Station, 4800 Concord Road, York, SC':-29745 s Plant Unit: 1 Owner Certification of Authorization: N/A- " Commercial-Service Date: 6/29/85-
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O EQA408 Page 2' Revision 0 December 9, 1992
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,1 t//m Manufacturer ~
StateLor. . National; = tJj: Manufacturer or_ Installer
.Se riqLtjp. Province No.- Ep_a r_d_fA -
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- DrLInstaller
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' Westinghouse Duke Power Co. .N/A N/A,
. Reactor Vessel Pressurizer _
Westinghouse DCPT-1911- N/A W18589-Steam Generator IA Westinghouse- DCPT-1902; N/A W11300
-Steam Generator 1B Westinghouse .DCPT-1901 N/A W11299 i N/A- W11302t Steam-Generator IC' Westinghouse DCPT-1904 ;
' Steam Generator 10_ Westinghouse DCPT-1903- -N/A. -W11301 :
l Reactor Coolant System Duke Power Co. NC N/A 126 Residual Heat Removal System Duke Power Co. ND -N/A 115 Safety-Injection System Duke Power co. NI N/A- 128 Chemical and Volume Control System Duke Power Co. NV N/A 127 Auxiliary Feedwater System Duke Power Co. CA N/A 121 Feedwater System Duke Power Co. CF N/A -120
-Refueling Water System Duke Power Co. FW N/A 91 ,
Main Steam-Supply'to Auxiliary Equipment System- Duke Power Co. SA N/A 114 Main Steam System Duke Power Co. SM N/A 122 Main Steam-Vent to a Atmosphere-System Duke-Power Co. SV N/A 96 J Containment Spray System Duke Power co. NS 'N/A 118
-Safety Injection Accumulator Tank 1A Westinghouse 0020 N/A- 310:
Safety Injection Accumulator Tank 18 Westinghouse 0019 N/A- 309 Safety Injection AccumulatorfTank IC Westinghouse 0018 N/A 308 , Safety injection- _ Accumulator Tank 10 Westinghouse 0021 N/A- 311 Unit 1 Duke Power Co. N/AL N/A 130 The Reactor Vessel, Steam Generators, Pressurizer, Reactor CoolantL
~
1.6 System Piping, Reactor Coolant Pumps, and Safety 1 Injection _ Accumulator Tanks were manufactured by' Westinghouse electric Corporation,- Pittsburgh, PA under purchase agreements from Duke _ Power Company. All other systems were fabricated and install.ed by Duke Power Company,
.422 S. Church St., Charlotte, NC 28201.
- 1. 7 - Authorized Nuclear Inservk _Insprctorfs)
-Name: 'R. N.MMcGill> 4 fhW Employee: The-Hartford . team Boiler '
Inspection.and Insurance Company-200 Ashford Center North, Suite 300 Atlanta,~GA 30338 EQA408 Page 3
-Revision 0--
December 9,_1992. 4 v-
. m
' /
' 2 PROGRAM: NIS'IRL ,AISIO2 DtJKE PCHER CCHPANY PAGE 18 \ FILE: CC07133 QUI.LITY ASSURANCE DEPAftTMENT DATE'12/10/92 - '
.' PL ANT r - CATAHBA UNIT 1 PRE-SERVICE At!D IN-SERVICE ItGPECTION SYSTEN
. KEY: ' ; ITEM NUMBER B16 CATAHUA 1 CLASS 1 REPORTABLE ITEtG OUTAGE 6 INSP PROC. HATERIAL DIAN./ CALIB
.ITEN nut 2ER . ID.PAPBER DRANING tAJHBERS . LOCS. REQ. tAJHDERS TYPE / GRADE THICK BLOCK CettENTS s==rzens==== smas==sassazzzzs==== mzzamazzmusam===msen as=== ==== ss==sess esass===== se==== es=== =========================esess
" B16.020.000 *********STEAN GENERATOR TUBING **** - *** ******* ***** . ***** ******* U-TUDE DESIGN ********
******************** [.1 ***** RANDCM 3% SAMPLE *******
B16.020.001 1SCA-TUDES CtM 1201.01-106 ET NDE-701 Iti 00.75 ----- SELECT CALIBRATION STANDAPS ' ( 00.044 PER YCLUME 1 SECTION 10.2 016.020.002 ISG8-TUBES' CtM 1201.01-106
- ET t40E-701 IN 00.75 SELECT CALIBRATICN STANDARD 00.044 PER VULUME 1 SECTIO 4 10.2 B16.020.003 ISGC-TUDES CtM 1201.01-106 ET NDE-701 Itf 00.75 ----- SELECT CALIBRATIO4 STANDARD 00.044 PER VOLUME 1 SECTID4 10.2 P16.020.004 ISGD-TUBES CtM 1201.01-106 ET NDE-701 IN 00.75 SELECT CALIBRATION STAT 4DARD 00.044 PER VCLUME 1 SECTION 10.2 W
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" P"OGRAft NISIRtRs24 AISIOZ' DLEE P0HER COMPA;W PAGE 32 ' ' FILE : : CC'07133 -
QUALITY ASSURANCE DEPARTMENT - DATE 12/11/92
- P LANT 3 .- :CATAHBA UtfIT 1 PRE-SERVICE AND IN-SERVICE INSPECTION SYSTEM KEY: ' ITEM NUMBER " G0 2 ' CATAHBA 1 AUGMENTED REPORTABLE ITEMS OUTAGE 6 ItGP PROC. tiATERIAL' CIAH./ CALIS .' ITEM NUMBER ' ID. PAREER- DRAHitC NUtBERS- LOCS. REQ. tPJMBERS TYPE / GRADE THICK DLOCK' COMMENTS armass=3 ssa asenss=ssssssssssssa ussrsmassssssssssssa massa s=s= ses=sssa ses====sms sanssa ass == susssssssssse==smssssssssssess . G02.001.000' ********* STEAM GENERATOR TUBE EXAMS *** ******* ***** . ***** ******* U-TUBE DESIGN ********
Ott PREMEATER SECTION [.1 * ***
- TUDES IN ROH 49 **** *** *
'C02.001.001 ISGA-TUDES- Citt 1201.01-106 ET t@E-701 IN 00.75 DONE MITH B16.020.001 SELECT 00.0 % CAL.STD.PER VOL.1 SECTION 10.2 i
G02.001.003 ISCC-RBES CtM 1201.01-106 ET NDE-701 IN 00.75 DetE NITH 816.020.003 SELECT
~ - 00.044 CAL.STD.PER VOL.1 SECTION 10.2 CO2.001.004. ISGD-TUDES CtM 1201.01-106 ET NDE=701 IN 00.75 DONE HITH B16.020.004 SELECT
- - - - - - - 00.0% CAL.STD.PER YCL.1 SECTION 10.2 4
a e - ,i. T % q p ., %W L
. . . ..- ~ .- . .- - . - - . - . . .- . - .
1 J/~ -2!0; l Status of:Reautred Insocctioni:- 20 M M'}N
* =
The completion-status-of. inspections _ required by.the(1980 ASME Section--
~
9 XI_ Code,1 including. addenda through Winter 1981, is summarized in this section; The-requirements are listed by the ASME_Section1XI examination-category as defined in-Table'IWB-2500-1=for Class-1;Inspectionsj nd"in-- IWC-2500-1_for Class 2_ Inspections. Augmented inspections'are-als_o. , included. Class 1 Inspections, 1
;Section
- XI _
Intpections Inspections Percentage Deferral
-CAlagnry Descrintion _.Re.quited__ .Insple_te.d_. C.nmoleted ALLquad_ -
BbA Pressure Rotalning '14 Welds 2.5 Welds 17.85% Yes. ; Welds in Reactor ' Vessel
.B-B-Pressure Retaining 8 Welds 6 Welds 75%. No-Welds in Vessels Other'than Reactor -
Vessel B-0 FullLPenetration 36 Inspections 18_ Inspections- 50% Partial . Welds of Nozzles
. in Vessels
'B-E Pressure Retaining 55 Welds 55 Welds 67% INo Partial Penetration Welds in Vessels B-F Pressure Retaining 46 Welds 32,5_ Welds 70.65% No Oissimilar Metal -
. Welds
,B-G-1 Pressure Retaining _370 Items 250 Items- 67.56%_ - .Y e s Bolting Greater >
Than-2 Inch-Diameter L B-G Pressure Retaining *59 Connections 42 Connections 71,18% No - L -Bolting 2 Inches and
- -Less in Diameter o
- Total connections includes CRDMS that are disassembled-
[ Y ? .
=__ -?
-EQA408 Page 1 Revision O -
December 9 1992-- E. . . _ . . . - . _ _ . . . _ _ ~ .e- .- .a -
a- . m myw W g3- ' L R& q& f2;0 ; )tAtys Lo f ~ Reaui red - In s par,1]Arn- %) )
. The Lcompletion statusLof inspections required by. theJ1980 A$ME Sect _f on -
~ XI Code,_ including addenda-through Winter:1981,-is~ summarized in this - section. The requirements are lir,ted by the ASME Section XI:: examination-category as defined in Table IWB-2500-1--for Class 1--inspections-and in-IWC-2500-1 for Class 2 Inspections, -Augmented inspections are also included. Class 1 Inspections Section
-X1 Inspections inspections Percentage Deferral; CAtMQI.Y Rtstr!niloa .J1envir;nt_. .Inm.pleiet - Comnieted_ A11nw.tt; B-A. Pressure Retaining 14 Welds 2.5 Welds 17.85% -Yes1 Welds in Reactor Vessel
. 0- B. Pressure Retaining 8 Welds 6 Welds 75% No-- ,
Welds in Vessels Other than Reactor - Vessel B-D. Ful'1 Penetration 36 Inspections 18 Inspections 50% Partial ".
= Welds of Nozzles in Vessels
'B-E - Pressure Retaining 55 Wolds 55 Welds 67% No Partial Penetration Welds in Vessels
B-F- Pressure Retaining 46 Welds 32.5 Welds 70.65% No'.
Dissimilar Metal Welds
- B-G-1 Pressure Retaining 370 Items 250 Items 67.56%L Yes .
Bolting Greater Than 2' inch .s
-Diameter B-G Pressure Retaining . *59 Connections 42 Connections 71.18% No ' ~
- Bolting 2 Inches-and Less in Diameter
- Total connections includes CROMS-that are disassembled
!~ i i y ,i, EQA408 Page 1 . 7 t
.s Revision _0.
l/ December 9,1992 Q 9
, . . . - . . ~ .- . . .. . _- . ,. ~ ,- . . - . - . ..
+
m-t i _. 3
.- f
- Class 11 Inspections _ (Continued):
- f()}
af"\ 'if -n ( jion - . Inspections = Linspections- Percentage Deferral
; GLt1991C fle.seriotio_n . Jie.gtLir_Cd_ -
_C9EPledad_. :C93P1010!L- AlIoWed-B-H- In_tegral Attachments 9: Attachments ~ 5 Attachments 155.55% "o for Vessels ,
~
B-J Pressure _ Retaining 201 Welds 157 Welds = -78 10%<
. : Ho ,
Welds in Piping -
.B-K-1 Integral Attachments None N/A -N/A 'N/A' for Piping, Pumps and Valves -s
-B-L-1 Pressure Retaining None N/A N/A N/A-Welds in Pump Casings ;
I B-L-2 Pump Casings Nor,e N/A- N/A: N/A B-M-1 Pressure Retaining 2 Welds 1 Weld' 50% Yesi -D Wolds in Valve Bodies a IB-M-2 Valve Body > 4 in, 7 Valves 5 Valves'- 71.42% 5Yes Nominal Pipe Size J' ~ 1 Interior of Reactor 3 Items 2 Items. - 66.66%; ENo - 3 Vessel B-N-2 Integrally Welded Core None N/A LN/A N/A' Support Structures and Interior Attachments to- , Reactor Vessels B-N-3 Removable. Core 1 Item None LO%' Yes-
= Support: Structures ,
8 Pressure Retaining- 3 Housings 3= Housings- -100%- lye s-: Welds in Control Rod , Housings l B-P- All. Pressure Retaining 'No. Components
~
System Leakage-Test -160 Components 1 -120 Components 75% System _Ilydrostatic Test 20 ComponentsL _0-Components' 0% O ~
.EQA408- Page 2' Revision 0 December 9J'1992 9 t?- r h -m a j 't"-Y
~ -.i 1
in Class 1-Inspections ~(Continued)-
-- e- -
l on .. XI: : Inspections ' Inspections : Percentage- Ocferral: ~' iGi105tQn DescriRMQD ORQOlud_- wCojapieted . Comoletet Al_loweIL
- B-0; Steam Generator Tubing 100% of Technical Specificattoris Het N/A:-
FN,91_ Class 1 Component 280 supports 214 Supports- -76.42% No: : Supports : t
'~
J@ , s N 4 4 4 9
- 5N
~:s.
b - EQA408 -- Page.3- !. Revision ~0-
=
December _9',- 1992-
. l n e ,--e n, --n+,......v - , . . w,,A r e--,; v - .<~,-v-.--S<~--~,,
,,w. m.,- -, -~~, , , - , - , ~ ~ - - v Or
t Class 2 Inspections'
-l v( E d- o n '-
Inspectioris Percentage. . Deferral XI' I n spec t1_ on s . 2 LAlagon ..D_eicI1Rtion _ReiluiteIL. _ Camplcied_ Cpap.le_tmi.; Allowed.-
.C-A Pressure-Retaining _ 9 Welds 6 Welds' 66.- 66% -- No-Velds in Pressure ,
_ Vessels
!C-B Pressure Retaining 6 Welds 4 Welds 66.66% No Nozzle Welds in i
- Vessels
- C-C Integral Attachments 33 Attachments 25 Attachments 75l 75' No- .{
for Vessels, Piping, , Pumps and Valves C-D- Pressure Retaining None N/A N/A: N/A Bolting Exceeding 2 Inches.in Otameter
.C-F-Pressure Retaining 343 Welds 271 Wolds' 79% So:
Welds in Piping f- Pressur,e Retairing 25 Welds 15 Welds 60% . No, p Welds in' Pumps and. Valves C-H All Pressure Retaining No-
-Components System or Component 70 Components 69 Components 98.57%
Functional Test System Hydrostatic Test -90 Components- 0_ Components .0% F1.02 Class 2 Component 568 Supports -417 Supports 76,93% No Supports O ECl,408 Page 4 Revision 0 December 9, 1992
- ' 7 ! Augmented' Inspections rO. ,
%/ DadMOD = ECICERIASE C&mP101R. i Reactor-Coolant Pump Flywheels: -100% oflTechnical-Specifications met-
~i 100% of. requirements for
~
' Steam Generator Tuoes on Preheater Section ;
Outages 1,.2, 3, 4, 5'&- 6, Main Steam Pipe Rupture Protection 100% of requirements for Outages 1, 2, 3, A, S &.- 6; Containment spray System 100%.of requirements:for Outages 1, 2, 3, 4, 5_&' 6. Thermal Stress Piping 100%-of req'uirements-for Outage-3, 4, 5 & 6. Safety injection Accumulator Nonles 100% of requirement for.: ,
-Outages 5 &-6,
- (O e
6 i I: l .- L t . b EQA400 Page 5: Revision 0 December 9',.1992 [ l { ..
..,,,,.a,,-.....,.. . , - , - - . . . - - - - - - , , - . - - , - - , - . . . , , . , . . ., - . , <
2
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'j" 3.0. . Eintl__In5AEY1Cf_.lasRest19n.filAn_.fsr__0xtage G The final ISI plan presented in this section lists all examinations credited for Outage 6 at Catawba 1. This includes ASME Section XI- Class 1, 2 and augmented-Inspections required by the plant technical:- H specifications.
The information shown below is a field description for the reporting format included in this section of the report: Item Number = ASME Section XI Tables IWB-2500-1 (Class 1),_ IWC-2500-1 (Class 2), IWD-2500-1 (Class 3) . IWF-2500-1 (Class 1, Class 2 and Class 3), and Augmented (Mquirements ! ID Number = Unique Identification Number Drawing Number = Location and/or Detail Drawing Locs. = Location Insp, Req. = Examination Technique - Magnetic Particle, Dye Penetrant, etc. Proc. Numbers -= Examination Procedures Material Type / Grade = General Description of Material. Diam / Thick = Diameter / Thickness Calib. Block = Calibration Block Comments = General and/or Detail Description 4 O Page 1 EQA408 Revision 0. December 9,- U92
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.[ "T n ~ PRCGAM: NISIR 6 2 SIO2. DtEE P0HED COMPANY PAGE 3 FILE: -CD07133 -
GUALITY ASSURANCE DEFARTMENT DATE 12/10/92-
-FLANT: CATANSA LNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTION SYSTEM KEY: ITEM PAJtBER B0Z .CATAMBA 1 INSERVICE INSFECTIcti LISTItG CUTAGE 6 INSP PRCC. MATERIAL DIAN./ CALIB ITEM *AJMbER ID NUMBER DRAMING PAJMBERS LOCS. REQ. PAJMBERS TYPE / GRADE THICK BLCCK CCit1ENTS 3s=======ss= ====ss=ssw========== smesss======ssessssa ===== ==s= ======== s======s== ====== sawr= ==============================
B02.000.000 *** PRESSURIZER AND MEAM GENERATCR *** ******* ***** ***** ***************************** VESSF.e. HELDS***** m ~. _. ~_ ** += me om**** mmm*w, 802.010.000 *** PRESSURIZER SHELL T5 HEAD HELDS- *** ******* ***** . ***** ********o****m*-****om m**momono* - . -_ m e m o m ** m m ****.*****- B02.011.000 *** PRES $URIZER SHELL TO HEAD HELDS *** ******* ***** ***** ************ m ********* m *o
~.-_
CIRCUMTERENTIAL***** ********mo m**** men m* B02.012.000 *** PRESSURIZER HELDS************** *** ******* *****. _._ ***** ************************** m LatGITUDINAL******** _ . _ ********************** m m ** B02.040.000 ** m m
- STEAM GENERATORS TUBESHEET *** ******* *****- . ***** ***o******************mem TU HEAD HELDS******* [._ *****************************
-i B02.040.001 ISGA-01-02 Ctat 1201.01-88 UT NDE-620 CS . 50301 STEAM GENERATCR IA CHAT #JEL CNN 1201.01-117 NDE-640 U3.HO HEAD TO TUBE SHEET 4
4 f --__a_a- .a-.uu.,,a--..__._ _ _ .
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~
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. PROGRAM PGSI SIOZ DtF.E P0HEa CD1PANY PAGE 4
~ \#.
FILE: CUD 7135- QUALITY ASSURAtCE DEPtRTMENT DATE 12/18/92
' PLANT: - CATA>BA UtHT I PRE-SERVICE At3D IN-SERVICE INSPECTIG1 SYSTEM -
KEY: ITEM FU1BER. 803 CATAHBA I ItGERVICE; INSPECTION LISTIrlG CUTAGE 6 ItGP PROC. MATERIAL DIAN./ CALIB ITEM tu1BER ID. IJUMBER DRANING NUMBERS LOCS. REQ. NUMBERS TYPE / GRADE THICK BLOCK ' COMMENTS
============ ==================== ==================== ===== *=== ======== ========== ====== ===== ===========2==================
w
~ B03.090.000 REACTOR VESSEL N0ZZLE TO VESSEL **** *** ******* ***** . ***** *****************nu m m n**
.NELDS m *** m m *** [ . "~~
- mmmum u m** n mm
.B03.100.000 REACTOR YESSEL NcZZLE INSIDE******* *** ******* ***** . * * * * * - ******************************
RADIUS SECTIM4****** '_~.~_ ************* - ******* m n ** B03.110.000 *** PRESSURIZER NcZZLE TO VESSEL **** *** **** m ***** _ , . _ uma ** m u m ********************* HELDS* m m ** m n
- _._ - m ********* m ** m m ** m **
- B03.120.000 .*** PRES $URIZER HUZZLE INSIDE RADIUS '*** ******* ***** _._ ***** ************************ m m SECTION=************ _ . _ ****************************** -
cB03.140.000 ********* STEAM CENERATORS N0ZZLE TO *** ******* ***** . ***** ** *m *** ** n n* * *** * *
- n= =m
- ItGIDE RADIUS ******* ~.~_,, *m*****m*n*
- m u n *m**
+
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PROGRAM: NISIRth SIC 2 DUKE PCHER COMPANY \ PACE S / '. FILE: C007133 QUALITY ASSURANCE DEPAZTMENT 'j DATE 12/IS/72 V' FLANT: CATANDA UNIT I PRE-SERVICE Af1D Iti-SERVICE ItGPECTICN SYSTEM ' KEY: ITEM tJUMBER BO4 CATAFOA I IPGERVICE ItGPECTION LISTItG CUTAGE 6 ItGP PROC. MATERIAL DIAM./ CALIB ITEM NUMBER ID. NUMBER DRAMING NUMBERS LCCS. REQ. NUMBERS TYPE / GRADE THICK BLCCK CM11ENTS
===r3sams==s ====s=============== =========se========= ==ssa ==== sass ==== ========== ====== ===== ==============e===2===========
804.010.000 REACTCR VESSEL PARTIAL PENETRATION * *** ******* ***** . ***** ********************** m e**** HELDS*************** ~.~ m m e************ m ** m *** B04.012.000 ******* PARTIAL PENETPATIGi********* *** ******* ***** _._ ***** ItGPECT AND DOCUMENT 100% CF CRD IFJEZLES********* _._ N0ZZLE HELDS G4 F4PD PRCEEDURE D04.013.000 ******* PARTIAL P ENETRATI m4 ** * *** * ** *** ******* ***** . ***** IPGPECT AND DOCUMENT 100% CF ItGTRUMENTATION***** [.-_ !40ZZLE HELOS ON PPD PRCCEDURE B04.020.000 *** PRESSURIZER HEATER PENETRATION ** *** ******* ***** ,,_,,._ ***** ItGPECT AND DOCUMENT 100% CF HELDS m ************ _._ FENT. HELDS CN NPD PROCEDUPE
-. : N ' PROGRAMr. NISIRAJISIO2 - DUKE P0HE2 CG1PANY PAGE - 6 ( -
- FILER CC07133, QUALITY ASStJAANCE DEPARTMENT , DATE 12/18/92 PLANTS: CATAHBA EUNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTICM SYSTEM KEYr ITEM NUMBER- B05 . CATANBA 1 ItGERVICE,ItJSPECTION LISTItG CitTAGE 6 INSP PROC. MATERIAL DIAM./ CALIB ITEM P 2 BER ID. P M BER DRAMItG PAJMBERS LOCS. REQ. NUMBERS' TYPE / GRADE TNICK BLOCK COMMEtGS ssssssss==ss amass ===sssssssss=== sss===ssssssssssssse es==s es== sensasss sass ====== sesssa suses assssssss====senssss===sasassa
.B05.010.000 REACTOR VESSEL NcZZLE TO SAFE END** *** ******* ***** ***** t M INAL PIPE SIZE 4 INCH A*1D**
BUTT NELDS********** [.. ~ _ GREATER ***********************
'B05.040.000 *** PRESSURIZER N0ZZLE TO SATE'END** *** ******* ***** ***** NOMINAL PIPE SIZE 4 INCH AND**
BUTT HELDS********** [.1 GREATER *******************=*=* BC5.040.004A IPZR-H4ASE CfM 1201.01-175/1 PT tide-35 Cr *SS 06.00 PRESSURIZER SAFETY NCZZLE CfM 1201.01-175/2 00.960 SAFE EfC , B05.040.005A IPZR-H4BSE CfM 1201.01-175/1 PT iAE-35 CS/SS 06.00 . PRESSURIZER SAFETY ICZZLE
- - CtM 1201.01-175/Z 00.960 SAFC END B05.040.006A IPZR-H4CSE CtN 1201.01-175/1 PT NDE-35 CS/SS .06.00 PRESSURIZER SAFETY tCZZLE CtM 1201.01-175/2- 00.960 SAFE END
- i B05.070.000 ********* STEAM GENERATUR PCZZLE TC* *** ******* ***** ***** P W INAL PIPE SIZE 4 INCH Arman SAFE END BUTT HELDS* [.1 . GREATER ***********************-
i 805.130.000 CLASS 1 PIPItG DISSIMILAR NETAL**** *** ******* *****- . ***** P M INAL PIPE SIZE 4 INCH ANDen BUTT HELDS********** [.~ , GREATER *********************** B05.130.017 1RPV-H52-01 CNN 1201.01-52/7 . UT NDE-610 rd/IN 06.25 50374 UHI TUBE O DEG. PC 90 TO 91: CPM 1201.01-51 00.625 UT FROM INCCNEL SIDE
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~
PROGRAM: HISIRtf M SIO2 DUKE PONEtt COMPT.NY PAGE '7 FILE: . -COO 7133 QUILITY ASSURANCE DEPAk'THEt3T - DATE 12/10/92 PLANT: CATAHBA 1RIIT 1 PRE-SERVICE AND IN-SERVICE ItGPECTION SYSdtt KEY: 'ITEtt tatBER B05 . _ . .CATAHBA 1 INSERVICE IPCPECTIC'4 LISTItG OUTAGE 6
. ItGP PROC. MATERIAL' 01AM./ CALIB
- ITEM NUMBER ID. tJUMBER DRAHING tRJMBERS LOCS. REQ. HUMBERS TYPE / GRADE THICK BLOCK CCit'ENTS
, ============ ================s=== ==================== ===== ==== ======== ========== se==== ===== ==============================
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PAGE 38 DUKE PCHER COMPAt# DATE 12/18/92 PROGRAM: NISIRuuAISIO2 ' Qt)ALITY ASSURAf1CE DEPARTMENT FILE: C007133 PRE-SERVICE AND IN-SERVICE ItCPECTIG4 SYSTEM PL At4T t CATANBA 12IIT 1 CATAHBA 1 ItEERVICE IPCPECTIGJ LISTIts CUTAGE 6 KEY: ITEN PJUMDER C05 ItGP PROC. MATERIAL DIAN./ CALIB COMMENTS DRAMIPC tJUMBERS LOCS. REQ. lAA1BERS T(PE/CRADE THICK BLOCK ===================== m ====re ITEN NUMBER 10. HUMBER ==== ======== ========== ====== =====
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C05.021.050 1CF17-04 CN-1CF-017 UT NDE-600 CS CN-1591-1.1 00.844 FEEDHATER SGIC C05.021.050A 1CF17-04 CN-1CF-017 MT NDE-25 ' CS 16.00 TERMINAL END CH-1591-1.1 00.844 FEEDHATER SG1C C05.021.051 1CF19-01 CN-1CF-019 . UT NDE-600 CS 18.00 50330 CH-1591-1.1 00.938
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C05.021.234 1NI80-01 - Crl-INI-080 UT NDE-600 SS 10.00 50312 --- CH-1562-1.1 01.000 C05.021.234A INI80-01' CN-INI-080- PT NDE-35 SS 10.00
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CALITY ASEAtCE CEPT.RTNENT CATE 12/10/92 * -
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C07.010.009 IFH STORAGE TK CH-1571-1.0 VT2 QAL-15 _ . , _ , , REFUELIPC MATER STORAGE TK _._ SYSTEM Ft3CTIG4AL TEST
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C07.030.014 1CN-1562-1.3 CN-1562-1.3 VT2 QAL-15 _ . _ _ HI SYSTEM - FUNCTIONAL TEST C07. 030. 015 1CH-1563-1.0 CH-1563-1.0 VT2 QAL-15 _._ ----- tG SYSTEM - FuCTIcttAL TEST C07.030.016 1CN-1570-1.0 CH-1570-1.0 VT2 QAL-15 ---- _._ ---- KF SYSTEM - FUNCTIONAL TEST C07. 030. 017 ICN-1571-1.0 CH-1571-1.0 VT2 QAL-15 _ _ . _ FH SYSTEM - FU4CTIONAL TEST C0 7. 030. 018 1CN-1572-1.0 CN-1572-1.0 VT2 QAL-15 - _._ NM SYSTEM - FUNCTIO 4AL TEST C 07. 030. 019 1CN-1556-1.0 CN-1556-1.0 VT2 QAL-15 _._ PB SYSTEM - FUNCTIO 4AL TEST C07.030.020 1CH-1592-1.1 CN-1592-1.1 VTi QAL-15 _._ CA SYSTEM - FUNCTIcitAL TEST C07.040.000 ********PIPIfG PRESSURE RETAlt4ING *w* *****me ***.* , **www
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- C07.050.001 ICHG PUMP 1A CN-1554-1.7 VT2 QAL-15 _._ CENTRIFUGAL CHARGItM PU1P
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- C07.050.002 ICHG PUMP IB CN-1554-1.7 VF2 QAL-15 _ . , _ , CENTRIFUGAL CHARGIPC PUMP
_ , . _ 18 - FUNCTIONAL TEST C07.050.003 1RHR PUNP 1A CN-1561-1.0 VT2 QAL-15 _._ RESIDUAL HEAT REM 0"/AL PUMP
, , _ . _ , _ 1A - FUICTICtIAL TEST C07. 050. 004 1RHR PUMP IB CH-1561-1.1 VT2 QAL-15 __,,._,,_ RESIDUAL HEAT ret 10 VAL PUMP
_ , , _ . _ IB - FtJNCTIONAL TEST C07.050.005 ISA Itu PMP 1A CH-1562-1.2 VT2 QAL-15 _ . _ _ SAFETY INJECTION PUMP 1A _._ FUCTIONAL TEST C07.050.006 ISA Itu PHP IB CN-1562-1.2 VT2 QAL-15 -- _ . , ._ _ SAFETY INJECTIC4 PUMP IB _,,._,,,_ FU CTI0t4AL TEST C07.050.007 1 SPRAY PUMP 1A CH-1563-1.0 VT2 QAL-15 _,,,_. CONTAltt1ENT SPRAY PUMP 1A _ _._,,,_,, FUNCTI0t4AL TEST -___.+em__ -
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001.012.004 1CN-1554-1.3 CH-1554-1.3 VT2 QAL-15 ----- FN SYSTEM - HYDRS TEST
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- I' L PROGRAMt HISIRb d M SIO2 DLZE PCHEft CCMPANY . PACE 57
' FILE: COO 7133 -
QU.*.LITY ASSURANCE DEPARTMENT DATE 12/10/92
' PLANT: 'CATAHBA tNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTION SYSTEM
. KEY: . ITEM PAABER D02 CATAHSA 1 ItGERVICE. ItGPECTIcti LIST 1tG CUTAGE 6
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============ ==================== ==================== ===== ==== ======== ========== ====== ===== ==============================
002.011.032 ICt4-2574-2.1 CH-2574-2.1 VT2 QAL-15 _._ RN SYSTEM 002.011.033 1Crl-2574-2.4 CN-2574-2.4 VT2 QAL-15 _._ RN SYSTEM D02.011.034 1Cf4 2574-2.5 C14-2574-2.5 VT2 QAL-15 _._ RN SYSTEM 002.011.035 1Cri-2573-1.1 Cid-2573-1.1 VT2 QAL-15 _._ KC SYSTEM D02.011.041 1Ct4-1565-2. 2 CN-1565-2.2 VT2 QAL-15 _._ ML SYSTEM 002.011.042 1CN-1569-1.0 CN-1569-1.0 VT2 QAL-15 _._ fM SYSTEM D02.011.043 1Cti-1609-4.0 Cil-1609-4.0 VT2 QAL-15 _._ VG SYSTEM. D02.011.044 1CN-1609-4.1 CN-1609-4.1 VT2 QAL-15 _._ VG SYSTEM l
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'002.011.050 1CN-1609-5.0 CH-1609-5.0 . VT2 QAL-15 _ . _ , , , VN SYSTEM 002.011.051 .3 CN-1574-1.4 VT2 QAL-15 _._ RN SYSTEM HYDROSTATIC TEST **** *** ******* ***** ***** ******************************
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' PLANT! CATAHBA " tJNIT l' PRE-SERVICE At3D IN-SERVICE INSPECTICN SYSTEM
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._,,_, ItCLS SHTS 2-6 FARTIAL 002.012.028 ICH-1609-3.1 CH-1609-3.1 VT2 QAL-15 _._ FD SYSTEM - HYDRC TEST
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~ PROGRAM: NISIRL , g SICZ 9JALITY ASSURANCE DEPARTMEd CATY 12/18/92
' FILER C007133 PLANT:C .CATAMBA LMIT I PRE-SERVICE AND IM-SERVICE IPGPECTION SYSTEM
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PAGE 79 DUKE PCHER CCMPANY DATE 12/1S/92 PRCGRAM: NISI N AISIO2 CUALITY ASSURANCE CEPARTMENT FILER CC07133 PLAf47: CATAHBA LNIT 1 PRE-SERVICE AFC IN-SERVICE ItGPECTION SYSTEh KEY: ITEM PAJ1BER F1. CATANBA 1 ItGERVICE IfGPECTIDN LISTIFFi CUTAGE 6 IfGP PRCC. MATERIAL DIAN./ CALIB CCMMENT*, ID. FAJMBER DRAMItG ta)MBERS LCCS. REQ. PAJMBERS TYPE / GRADE THICK BLCCK ==================_=========== ITEM HUP 1 DER ======e= ========== ====== =====
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- PAGE 80
'AISIO2 DUKE PCHER COiPANY DATE 12/18/92 I PROGRAM' NISIRA QUALITY ASSURA?JCE OEPAR - .
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F1.03.577A 1-R-KC-0535 CN-1492-KC-0 %R VT QAL-14 06.00 RICID SUPPORT F1.03.578 1-R-KC-0537 CN-1492-KC-0%R VT QAL-14 06.00 RIGID SUPPORT
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4.0 Result L91_I nspert_1911Lfrr f o rnteiSu r i n g_qu t a gt6 The results of each inspection shown in the final ISI Plan (Section 3 of this report) are included in this section. The completion date and status for each inspection are shown. All inspections revealing reportable indications are described in further detail in Section 5, 6, or 7 as applicable. The information shown below is a field description for the reporting format included in this section of the report: Item Number = ASME Section XI Tables IWB-2500-1 (Class 1), lWC-2500-1 (Class 2), IWD-2500-1 (Class 3), IWF-2500-1 (Cla:s 1, Class 2 and Class 3), and Augmented Requirements ID Number = Unique Identification Number Inspection Date = Date of Examination Inspection Status CLR = Clear REC = Recordable REP = Reportable inspection Limited , L = Limited
- = No Geo, Ref. = Geometric Reflector N = No _
Y = Yes Comments = General and/or Detail De:cription
'O EQA408 Page 1 Revision 0 December 9, 1992 i
_______ _- - - - - _ _ _ - - _ - - _ _ - - _ - - - - - - - - - - _ - - - - - . - - -- - u
PAGE 1 AISIO4 DUKE P0HER COMPAPW DATE 12/1S/92 PROGRAMt NISIR- > GUALITY ASSURANCE DEPARTMENT FILE: C007133 PLAffT: CATAHBA LNIT 1 PRE-SERVICE AND IN-SERVICE ItGPECTION SYSTEM KEYr ITEM tAJMBER B02 CATANSA 1 ItGERVICE IPCPECTIG4 RESULTS CUTAGE 6 INSPECTICH IPCPECTIG4 ItGPECTIOff GEU. DATE STATUS LIMITED REF. COMMENTS ITEH IFJMBER ID IAJMBER ========== ===ns==ssa ==== ======================s m===== ass ====s==se ===sms==ss==== sasses s========s 07/16/92 CLR L Y B02.040.001 ISGA-01-02 l L__ _ _
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- ITEN PAJMBER ID PAJtBER . DATE STATUS LIMITED .REF. CmtfENTS
- assunsmessas assssses==ss==sssses esssumes== 3s======== =========3 ==== ====================s======ssa 805.040.004A IPZR-W4ASE 08/19/92 CLR ,,
N B05.040.005A 1PZR-H4BSE -- 08/19/92 CLR ._ H B05.040.006A IPZR-W+CSE - 08/19/92 CLR _ H 805.130.017 1RPV-H52-01 08/19/92 CLR _, N B05.130.017A 1RPV-N52-01 08/19/92 CLR _ H "B05.130.0178 1RPV-H52-01 08/19/92 .. CLR ,, H B05.130.018 1RPV-H52-02 08/19/92 CLR _ H , B05.130.018A .1RPV-H52-01 08/19/92 CLR _ H B05.130.018d 1RPV-H52-02 08/19/92 CLR _ N
'B05.130.019 1RPV-H52-03 07/27/92 CLR _
H B05.130.019A 1RPV-H52 07/26/92 CLR _ H B05.130.01aB 1RPV-H52-03 07/27/92- CLR _ N B05.130.020 1RPV-H52-04 08/19/92, CLR _ N B05.130.020A 1RPV-H52-04 08/19/92 CLR _ N B05.130.0208 '1RPV-H52-04 08/19/92 CLR _ N
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ITEH NUMBER .ID NUtBER DATE STATUS LIMITED REF. Cat 1ENTS
============ ==================== ==========. ========== ========== ==== ==============================
B06.180.003 1RCP-IC-F 07/22/92 CLR _ N
- BD6.190.001 1RCP-1A-FLAICE 08/08/92 CLR ,,,
N B06.190.002 1RCP-18-FLAPCE 08/03/92 CLR _ N
'B06.190.003 1RCP-1C-FLAFCE 07/31/92 CLR' _
N B06.190.004 1RCP-10-FLNJGE 08/08/92 CLR, _ N
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============ ==================== === ====== ========== ========== ==== ==============================
B07.060.003 1RCP-IC-S 07/17/92 Ct.R _ N B07. 060. 007 1RCP-1C-it 07/17/92 CLR _ H B07.070. 001 1HC-l' 07/17/92 CLR _ N B07.070.002 110-2 07/17/92 Ca.R _ N B07.070.003 INC-3 07/17/92 CLR _ N
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FILE: CC07133 QUALITY ASSURAtCE DEPARTMENT ~ / DJ4TE 12/7 b/ PLANT: CATAHBA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTICN SYSTEM KEY: ITEN PAA1BER B09 CATAHBA 1 IPCERVICE ItGPECTIcti REStJLTS CUTAGE 6 ItGPECTION ItGPECTICH IPCPECTICH GEU. ITEM NUMBER ID NUMBER DATE STATUS LIMITED REF. CCit1ENTS n==zasszs ss ======ss=====rs===== ====ss=ses as======ca ========== ==== =====================s==s=== B09.011.063 IPC224-01 08/19/92 CLR _ Y B09.011.063A INC224-01 08/19/92 CLR _ H B09.011. 064 IPC224-02 08/19/92 CLR _ Y B09.011.064A ItC224-02 08/19/92 CLR _ N B09.011.065 ItC227-01 08/19/92 CLR _ Y B09.011.065A ltC227-01 08/05/92 CLR _ N B09.011.066 IPCZ27-02 08/19/92 .CLR _ Y B09.011.066A INC227-02 C8/05/92 CLR _ H B09.011.067 INC258-01 08/19/92 CLR _ Y B09.011.067A lt3C258-01 08/19/92 CLR _ N B09. 011.068 ltC286-01 08/19/92 CLR _ Y 209.011.068A ltC286-01 08/19/92 CLR _ N B09.011.069 INC286-02 08/19/92 CLR _ Y B09.011.069A ItC286-02 08/19/92 CLR _ N B09.011.070 ItC286-03 08/19/92 CLR _ Y
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ITEM NUMBER -ID NUMBER DATE- STATUS LIMITED REF. COTENTS sms=sssssssa assssssssssssssssses assass==ss assanssums ========== ==== sasssssssssssss=====sssssssssa 809.011.070A INC286-03 08/19/92 CLR _ H B09.011.071 INC286-04 07/27/92 CLR L Y B09.011. 071A INC256-04 07/26/92 CLR _ N B09.011.321 17G149-06 08/18/92 CLR _ Y B09.011.321A INI149-06 08/17/92- CLR _ N B09.011.322 INI149-07 08/18/92 CLR _ Y B09.011.322A IfG149-07 08/17/92 CLR _ N B09.011.323 1NI149-08 08/18/92 CLR _ Y B09.011.323A INI149-08 08/37/92 CLR _ N B09.011.324 1NI152-02 08/08/92 CLR ._ Y B09.011.324A .INI152-02 07/28/92 CLR- _ N B09.011.325 1NI152-03 08/08/92 CLR. _ Y B09.011.325A 17G152-03 07/28/92 CLR _ N B09.011.326 17E152-04 08/C8/92 CLR' _ Y B09.011.326A INI152-04 07/28/92 CLR _ N m-+Li A
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. FILE! CU07133 SIO4 CUKE PS C COMPANY CUALITY ASSURANCE CEPARTMENT (x s) P:A;:E 27 DATE lu1GX2 ['q,-) PLANT: CATAHatA tRfIT 1 PRE-SERVICE AND IN-SERVICE IPCPECTIO4 SYSTEM KEYt ITEM NUMBER D02 CATA>BA 1 IPGERVICE I?CPECTIai RESULTS O!JTAGE 6 IPGPECTICH I?GPECTInt IPGPECTIO4 GE *J. ITEM NUMBER - IDPSEBER DATE STAT 15 LIMITED REF. CDT*ENTS emus ====neen ====r33e============ =======e== ====3me=== ===s====== er== =e====e==r3=============m1e=== 002.011.026 1CN-1609-1.0 02/19/92 REC _ N D02.011.025 1CH-1609-2.0 02/06/92 CLR _ N D02.011.026 1CN-1609- 2.2 02/19/92 CLR _ N D02.011.027 1CH-1609-3.0 02/06/92 CLR _ N - 002.011.028 1CN-1609-3.1 02/19/92 CLR _ N D02.011.029 104-1593-1.2 02/20/92 CLR _ N D02.011.031 ICN-2574-2.0 01/16/92 CLR _ N D02.011.032 1CN-2574-2.1 01/16/92 CLR _ N 002.011.033 1CN-2574-2.4 01/16/92 CLR _ N
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F1.01.465 1-R-rG-1307 07/2U92 CLR _ N F1.01.466 1-R-tG-1308 07/2U92 CLR _ N F1.01.467 1-R-tG-1309 07/22/92 CLR _ N F1.01.468 1-R-NI-1310 07/22/*2 CLR _ N F1.01.469 1-R4G-1311 07/2U92 CLR _ N F1.01.470 1-R-tG-1317 09/04/92 CLR _ N F1.01.471 1-R-tn-1322 07/22/92 CLR _ N F1.01.472 1-R-tG-1304 07/22/92 CLR _ N F1. 01.473 1-R-tG-1305 07/ZU92 CLR _ N F1. 01.4 74 1-R-tG-1306 07/22/92 CLR _ N F1.01.475 1-R-tG-1313 07/22/92 CLR _ P4 F1.01.477 1-R-tC-1316 07/22/92 CLR _ N F1.01.701 IPZR-SKIRT 09/04/92 CLR _ N F1.01.702 1PZR-LUGS 09/04/92 CLR _ N F1.01.704 IPZR-SUPPCRT 09/04/92 CLR _ N
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F1.02.079 1-R-CA-1551 07/17/92 CLR _ N F1.02.080 1-R-CA-1552 07/17/92 CLR _ N F1.02.082 1-R-CA-1562 07/17/92 CLR _ M F1.02.083 1-R-CA-1563 07/17/92 CLR _ N F1.02.084 1-R-CA-1564 07/17/92 CLR _ N F1.02.085 1-R-CA-1565 07/17/92 REC _ N F1.02.086 1-R.CA-1566 07/17/92 CLR _ N F1.02.087 1-R-CA-1643 07/17/92 CLR _ N F1.02.088 1-R-CA-1644 07/17/92 CLR _ N F1.02.169 1-R-CT-1563 07/17/92 CLR _ N F1.02.170 1-R-CF-1564 07/17/?2 CLR _ N F1.02.171 1-R-CT-1565 07/17/92 CLR _ N F1.02.172 1-R-CF-1566 07/17/92 CLR _ N F1.02.173 1-R-CF-1567 08/11/*2 CLR _ N
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F1.02.868 1-R-SM-1561 07/23/92 CLR _ N F1.03.126 1-R-CA-0031 06/25/92 CLR _ N F1.03.127 1-R-CA-0033 06/25/92 CLR _ N F1.03.128 1-R-CA-CO34 06/25/92 CLR _ N F1.03.129 1-R-CA-0035 06/25/92 CLR _ N F1.03.130 1-C-CA-0037 06/25/92 CLR _ N F1.03.131 1-R-CA-0055 06/25/92 CLR _ N F1.03.132 1-R-CA-0056 06/25/92 CLR _ N F1.03.133 1-R-CA-0008 06/25/92 CLR _ N F1.03.134 1-R-CA-0009 06/25/92 CLR _ N F1.03.135 1-R-CA-0011 06/29/92 CLR _ N F1.03.136 1-R-CA-0012 06/29/92 CLR _ N F1.03.137 1-R-CA-0013 06/19/92 CLR _ N F1.03.138 1-R-CA-0014 06/29/92 CLR _ N F1.03.139 1-R-CA-0016 06/29/92 CLR _ N
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F1.03.140 1-R-CA-0017 06/2?/92 CLR _ N F1.03.141 1-R-CA-C018 06/25/92 CLR _ N F1.03.142 1-R-CA-0019 06/29/?2 CLR _ N F1.03.143 1-R-CA-0020 06/29/92 CLR _ N F1.C3.144 1-R-CA-0021 06/25/92 CLR _ N F1.03.145 1-R-CA-0022 06/25/92 CLR _ N F1.03.146 1-R-CA-0023 06/25/?Z CLR _ N F1.03.147 1-R-CA-0025 C6/25/92 CLR _ N F1.03.148 1-R-CA-0027 06/25/92 CLR _ N F1.03.149 1-R-CA-0029 06/25/92 CLR _ N F1.03.150 1-R-CA-0054 06/25/92 REC _ N F1.03.151 1-R-CA-0001 C6/2?/*2 CLR _ N F1.03.152 1-R-CA-0002 06/29/92 CLR _ N F1.03.153 1-R-CA-0003 A/29/92 CLR _ M F1.C3.154 1-R-CA-0004 06/25/92 CLR _ N
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F1.03.155 1-R-CA-0005 06/25/92 CLR _ N F1.C3.156 1-R-CA-0006 06/25/?2 CLR _ N F1.03.236 1-R-LD-0036 06/24/92 CLR _ N F1.03. 237 1-R-LD4038 06/24/*2 CLR _ N F1.03.238 1-R-LD-0039 06/24/92 CLR _ N F1.03.239 1-R-LD-0043 06/24/92 CLR _ N F1.03.240 1-R-LD-0084 06/24/92 CLR _ N F1.03.241 1-R-LD-0085 06/24/?2 CLR _ N F1.03.242 1-R-LD-COS6 06/24/92 CLR _ N F1.03.243 1-R-LD-0088 06/24/92 CLR _ N F1.03.244 1-R-LD-0090 06/24/?2 CRR _ N F1.03.343 1-R4D-0053 06/24/92 CLR _ N F1.03.344 1-RfD-00 77 06/24/92 CLR _ N F1.03.345 1-R 4D-0078 C6/24/92 CLR _ N __, F1.03.346 1-R-KD-0079 06/24/92 CLR _ N
i PAGE 40 DUKE PdkER CDPAfff CATE 12/18/*2 FRCURArt: NISIR' w ISIO4 GUALITY AS'A:RANCE OEPARTMENT FILE: CC07153 PLA*tT : CATAMBA tR4IT 1 FRE-SEPVICE AFC IN-SERVICE ItGPECTID4 SYSTEM KEY: ITEM NUMBER F1. CATA>BA 1 IfGERVICE ItGPECTID4 RESULTS CUTAGE 6 ItGPECTID4 I'CPECTID3 ItG*,TCTIDI GEU. DATE STATLG LIMITED- FEF. Cert 1ENTS ITEM PfJMBER ID PUTER rer======= ========== ==== ========e========e1===========
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PPCGRAM: NISI FILE: PLANT: CC07133 ISIO4 CATAMBA UNIT 1 OUKE PCHE2 COMPANY QUALITY ASSURAPCE DEPARTMENT G PRZ-SERVICE AtC IN-SERVICE INSPECTIQ4 SYSTEM FACE 41 DATE 12/18/92 N KEY: ITEM t0MBER F1. CATAMBA 1 ItGERVICE IPCPECTIG4 RESULTS CUTAGE 6 IPCPECTIC4 I?CPECTImi IPCPECTIO4 GEU. ITEM 70MBER ID 10MBER OATE STATUS LIMITED REF. CQ91ENTS
============ ==================== ========== ========== ========== e=== ===========____.e======ee=====
F1.03.564 1-R-KC-0287 06/24/92 CLR _ N F1.03.564A 1-R-KC-0288 06/24/92 CLR _ N _ F1.03.565 1-R-KC-0290 06/24/92 CLR _ ie F1.03.565A 1-R-KC-0292 06/24/92 CLR _ N F1.03.566 1-R-KC-0293 06/24/92 CLR _ N F1.03.566A 1-R-KC-0296 06/24/92 CLR _ N
.F1.03.567A 1-R-KC-0701 06/24/92 CLR _
N F1.03.568 1-R-KC-0702 06/24/92 CLR _ N F1.03.568A 1-R-KC-0041 06/24/92 CtR _ N F1.03.569 1-R-KC-0042 06/24/92 CLR _ N F1.03.569A 1-R-KC-0044 06/24/9; CLR _ N F1.03.570 1-R-KC-0046 06/24/92 CLR _ N F1.03.570A 1-R-KC-0047 06/24/92 CLR _ N F1.03.571 1-R-KC-0068 06/24/92 CLR _ N 11.03.571A 1-R-KC-0071 06/24/92 CLR _ N
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{ , PROGRAM: NISI ISIO4 DUKE PCHER COMPANY ' %,, FACE 42 (,/ FILE: CC07133 QUALITY ASSURANCE DEPARTMENT DATE 12/10/92 PLAffT: CATAHBA tAiIT 1 PRE-SERVICE AND IN-SERVICE ItGPECTION SYSTEM KEY: ITEM ffJMBER F1. CATAHDA 1 ItGERVICE IfGECTID4 RESULTS CUTAGE 6 If 6PECTID4 ItSPECTION ItGPECTION GEU. ITEN NUMBER ID NUteER DATE S'-TUS LIMITED REF. CD1MENTS
=re========= ===s================ ========== === u===== ========== ==== =======================e======
F1.03.572 1-R-KC-0521 06/24/92 CLR _ N F1.'3.572A 1-R-KC-0522 06/24/92 CLR _ N F1.03.573 1-R-KC-0523 06/24/92 CLR _ N F1. 03.573 A 1-R-KC-0524 06/24/92 CtR _ N F1.03.574 1-R-KC-0526 06/24/92 REC _ N F1.03.574A 1-R-KC-0552 06/24/92 CLR , N F1.03.575 1-R-KC-0710 06/24/92 CLR _ N F1.03.575A 1-R-KC-0530 06/24/92 CLR _ N F1.03.576 1-R-KC-0531 06/24/92 CLR _ N F1.03.576A 1-R-KC-0533 06/24/92 CLR _ N F1.03.577 1-R-KC-0534 06/24/92 CLR _ N F1.03.577A 1-R-KC-0535 06/24/92 CLR _ N F1.03.578 1-R-KC-0537 06/24/92 CLR _ N F1.03.578A 1-R-KC-0538 06/24/92 CLR _ N F1.03.579 1-R-KC-0539 06/24/92 CLR _ N
PAGE 43 ISIO4 DUKE P0HER CCMPANY DATE 12/18/92 PROGRAM: NISIR QUALITY ASSURAtaCE CEPARTMENT FILE! COO 7133 PLArtT: CATAHBA UNIT 1 PRE-SEFVICE APJD IN-SERVICE ItGPECTIO4 SYSTEff KEY: ITEM NUMBER F1. CATAMBA 1 ItGERVICE IfCPECTION RESULTS OUTAGE 4 IPCPECTION IfCPECTIt24 I?GPECTIQ4 CEO. DATE STATUS LIMITED REF. CCMMENTS j ITEM PFJMBER ID P4 UMBER ses=ss==rs szsssss=== ==== ==e===-==ezzss==z3:eze===.===== me=szsssss== ess=ssazzzssssssssse me====ss== j I 06/24/92 CLR N _ F1.03.579A 1-R-KC-0540 _ i f F1.03.580 1-R-KC-0543 06/24/92 CLR _ N
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l 06/24/92 CLR N F1.03.580A 1-R-KC-0544 , N l 1 I F1.03.581 1-R-KC-0517 06/24/92 CLR _ CLR N l F1.03.581A 1-R-KC-0518 06/25/92 _ 1-R-KC-0520 06/24/92 CLR _ N f, rl.03.582 06/24/92 CLR N l F1.03.582A 1-R-KC-0499 _ 06/24/92 CLR N F1.03.583 1-R-KC-0500 _ 1 06/24/92 CLR N F1.03.583A 1-R-KC-0501 _ I 06/24/92 CLR N F1.03.584 1-R-KC-0502 _ 06/24/92 CLR H F1.03 584A 1-R-KC-0503 _ 06/24/92 CLR N F1.03.585 1-R-KC-0504 _ 06/24/92 CLR N F1.03.585A 1-R-KC-0505 _ 06/24/92 CLR N F1.03.586 1-R-KC-0506 _ 06/24/92 CLR N F1.03.586A 1-R-KC-0561 _ 4 i > o i-
PAGE 44 ISIO4 DUKE P0HER CDPANY DATE 12/18/92 PROGRAM: NISIRL QUALITY ASSURANCE DEPARTMEt' FILE: CC07131 PLANT: CATAHRA UTIT 1 PRE-SERVICE AND IN-SEPVICE INSPECTIG4 SYSTEM ! KEYr ITEM fM BER F1. CATAHBA 1 IfGERVICE INSPECTIGJ RESULT 3 DL1TAGE 6 ItCPECTIG1 ItCPECTIml ItGPECTImi GES. DATE STATUS LIMITED REF. COMMENTS ITEM tL91BER ID t&1BER ========== ========== ==== ==============================
=======a==== ==================== =========s 06/24/92 CLR N F1.03.587 1-R-KC-0562 _
06/24/92 CLR N F1.03.587A 1-R-KC-0563 _ 06/26/92 CLR N F1.03.813A 1-R-RN-0294 _ 06/25/92 CLR N F1.03.814 1-R-RN-0295 , 06/25/92 CLR N F1.03.814A 1-R-RN-0296 _ 06/25/92 CLR N F1.03.815 1-R-RN-0297 _ 06/25/92 CLR N F1.03.815A 1-R-RN-0298 _ 06/25/92 CLR N F1.03.816 1-R-RN-0299 _ 06/26/92 CLR N F1.03.816A 1-R-RN-0300 _ CLR t1 F1.03.817 1-R-RN-0301 06/25/92 _ 06/25/92 CLR N F1.03.817A 1-R-RN-0302 _ 07/29/92 CLR N F1.03.818 1-R-RN-0304 _ 06/25/92 CLR N F1.03.818A 1-R-RN-0305 _ 06/25/92 CLR N F1.03.819 1-R-RN-0369 _ 06/25/92 CLR N F1.03.819A 1-R-RN-0370 , I I I
PAGE 45 CUKE PCHER CetPAPN DATE 12/18/92 PROGRAM: NISI v ISIO4 GUALITY ASSURANCE DEPARTMENT FILE: CC07133 PL At4T t CATAHBA LNIT 1 PRL-SERVICE AND IN-SERVICE IPGPECTION SYSTEM KEYr ITEM NUMBER F1. CATAHBS 1 ItGERVICE ItGPECTICH RESULTS CPJTAGE 6 I!GPECTION ltGPECTION ItGPECTION GEO. DATE STATUS LIMITED REF. CCMMENTS ITEM NUMBER ID NUMBER ===c====== ========== ==== ==============================
========s=== ==================== ==========
06/25/92 CLR N F1.03.820 1-R-RN-0371 _ 06/25/92 CLR N F1.03.820A 1-R-RN-0290 _ 08/05/92 CLR N F1.03.821 1-R-RN-0291 _ 08/05/92 CLR N F1.03.821A 1-R-RN-0292 _ 08/05/92 CLR H F1.03.822 1-R-PJ4-CZ93 _ 06/25/92 CLR N F1.03.822A 1-R-RN-0326 _ 06/24/92 CLR N ta.03.823 1-R-RN-0354 _ 06/25/92 CLR N F1.03.823A 1-R-RN-0367 _ 06/25/92 CLR H F1.03.824 1-R-PN-0368 _ 06/25/92 CLR N F1.03.824A 1-R-RN-0469 _ 06/25/92 CLR N F1.03.825 1-R-RN-0470 _ 14 F1.03.825A 1-R-RN-0483 06/25/92 CLR _ 06/25/92 CLR N F1.03.826 1-R-RN-0489 _ 06/25/92 CLR H F1.03.826A 1-R-RN-04?O _ 06/25/92 CLR N F1.03.827 1-R-RN-0491 _
m_ p~ , N PROTJLM: NISIRG .AISIO4 00KE PCMER CD1PANY % - PAGE 44 : . FILE: C007133 . ' QUALITY ASSURANCE DEPARTMENT- DATE 12/10/92
; PLAI47 'CATAHBA~ UttIT 1 PRE-SERVICE AND IN-SERVICE INSPECTIGJ SYSTEM KEY:- ITEM ffJtBER F1. .CATAleA 1 INSERVICE,IPGPECTION RESUL13 t'UTAGE 6 ItGPECTI@i IPSPECTIM8 ItGPECTIG4 GES.
. ITEM NUtBER ID NUtBER- DATE . ' STATUS LIMITED REF. C0tt1ENTS
===========s ==msss== man ===sn3mse ====3ss=== sss======= ========== ==== ==========sm===== n===========
F1.03.827A 1-R-RN-0527 06/25/92 CLR ,, N F1.03.828 1-R-RN-0528 06/25/92 CLR- _ N F1.03.828A 1-R-RN-0529'~ 06/25/92 CLR , N
.F1.03.829 .1-R-RN-0589- 06/24/92 CLR _
N
'F1.03.829A> R-RN-0590 *D6/24/92 CLR _ N F1.03.830 1-R-RN-0591 '06/24/92 ~ REC _
N F1.03.830A 1-R-RN-b592 06/24/92 CLR _ N F1.03.831 1-R-RN-0593 06/24/92 .CLR _ N
'F1.03.831A 1-R-RN-0594 06/24/92 .CLR ~ _
N F1.03.832 1-R-RN-0595 06/25/97 CLR. _ N F1.03.832A .1-R-RN-0596 06/24/92 CLR _ N F1.03.833 1-R-RN-0649- 06/24/92 CLR _, N-F1.03.833A 1-R-RN-0650 06/24/92-' ' REC _ N
. . i F1.03.834 '1-R-RN-0597 '06/24/92 CLR _
N F1.03.834A 1-R-RN-0598 06/24/92 CLR _ N
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' PROGRAM: NISI ISIO4 Ot#.E POER COMPANY \ l PAGE 47 k I FILE: Cc07133 CUALITY ASSURANCE DEPARTMENT ~g DATE 12/10/T2 ' -'
PLAffT CATAHSA (AiIT 1 PRE-SERVICE AND I?4-SERVICE ItGPECTID4 SYSTEM KEY: ITEM PAJMDER Gol CATAHBA 1 ItGERVICE. IrCPECTInd RESULTS OJTAGE 6 ItGPECTImi ItGPECTIm4 IFEPECTInf GEU. ITEN tJUMBER ID NUMBER DATE STATUS LIMITED REF. CCMMENTS
======= sam == =========ssa::s===== =srs====== =======s3= == ======= ==== =========================_ ===
G01.001.001 1RCP-1A 07/22/92 CLR L N G01.001.002 1RCP-IB 08/02/92 CLR L N C01.001.002A 1RCP-1B 08/02/92 CLR _ N l l
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g . --PROGRAMrNI3 IRE s 3SIO4 -DUKE PetE2 CMPAPff k/ - Pt.GE 48 .k
' FILER - Ctr07133 QUALITY ASSURANCE DEPARTNENT DATE 12/10/92 -
3 plt.NT: .: - CATAHBA ' UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTICH SYSTEM KEY: . ; ITEM PUt1BER G02 CATA}eA 1 INSERVICE 1FCPECTION RESULTS CLTAGE 6 IPCPECTION IN5PECTION TPCPECTION GEU.
- ITEM NUMBER 10 tRA1BER DATE- LIMITED STATUS. REF. Cott1ENTS
====szanss== ==ssssammass======== ss======ss ========== sus ==ss=== ==== ss==========ssss=========sessa ,
G02.001.001. '1SGA-TUBES. 08/24/92 REP _ tl
- G02.001.002 ISGB-TUBES 08/24/92 REC _ N ,
G02.001.003 ISGC-TUBES 09/01/92 REP _ N G02.001.004 ISCO-TUBES ' 09/05/92 REP _ N
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PAGE 49 DtKE PO4ER COMPANY DATE 12/18/92 PROGRAM:'NISIRUf - -ISIO4 GUALITY ASSURANCE DEPARTMEffT FILE: C007133 PRE-SERVICE A?JD IN-SERVICE ItCPECTIG4 SYSTEM PLAtiT: CATAteA Ut4IT 1 CATAHBA 1 ItGERVICE ItGPECTION RESULTS CLITAGE 6 KEY: ITEM PJUMBER G03 ItGPECTION ItGPECTICN GEU. ItGPECTION LIMITED REF. CC?t1ENTS DATE STATUS = == ===================ssesns===== ITEM trJMBER 10 NUMBER ==ssessens iss=======
============ mes=======ssezzssw== ====ss====
L Y G03.001.036 ISM 37-01 08/31/92 CLR l N ISM 37-01 08/25/92 CLR _ C03.001.036A CLR L Y 003.001.037 ISM-7D-A 08/31/92 CLR N C03.001.037A ISH-7D-A 08/27/92 _ L Y ISM 37-04 08/31/92 CLR _ G03.001.038 CLR N G03.001.038A ISH37-04 08/25/92 _ CLR L N ISM 37-05 08/31/92 G03.001.039 CLR N ISM 37-05 08/25/92 _ G03.001.039A CLR Y ISH-60-A 09/02/92 , G03.001.040 CLR N ISM-6D-A 08/25/92 _ G03.001.040A CLR N G03.001.041 ISM 38-01 09/02/92 _ CLR N ISH38-01 08/25/92 _ G03.001.041A CLR L Y ISM 38-02 09/02/92 G03.001.042 CLR N ISM 38-02 08/25/92 _ G03.001.042A CLR L N C03.001.043 ISM-4D-C 09/03/92 i
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PAGE 50 DUKE PCHER COMPAPN DATE 12/18/92 PROGRAM: 741SIRtk J5104 CUALITY ASSURANCE DEPART?CNT FILE: COO 7133 CATAHBA UNIT 1 PRE-SERVICE AND IN-SERVICE IPEPECTIC4 SYSTEM PLANT: CATAHBA 1 IFEERVICE IPCPECTIG4 RESULTS CUTAGE 6 KEY: ITErt NUMBER C03 IPGPECTION IfGPECTIO4 CEO. ItGPECTION REF. COMMENTS DATE STATUS LIMITED =======ss=======e====ms3====ss ITEM NUMBER ID fJUMBER s========= es====s=== ==== z===ss====== ==sss====ssssazzs=== ===sszzz== CLR N G03.001.043A ISM-4D-C 08/25/92 _ L Y G03.001.044 1SM AD-B 09/02/92 CLR N G03.001.044A ISM-4D-B 08/25/92 CLR _ l 09/02/92 CLR L N G03.001.045 ISM-4D-A N G03.001.045A ISM-4D-A 08/25/92 CLR _ L Y G03.001.046 ISM 38-05 09/02/92 CLR CLR N 1 Sit 38-03 08/25/92 _ G03.001.046A
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FILE ~ ' COO 713(3J SIO4 - QUALITY ASSURAPCE DEPARTHENT DATE 12/12/92 PLANT: CATAHBA-'tJNIT 1 PRE-SERVICE AND IN-SERVICE DGPECTION SYSTEM KEY: ITEM NUMBER G05 CATAHaA 1 ItGERVICE DGPECTION RESULTS CUTAGE 6 ItGPECTION ItGPECTION ItGPECTION GEO. ITEM ffJHBER ID PAJtEER DATE STATUS L1HITED- REF. COMMENTS
==ssansazzes ==========ses=zs==== ======sss= szzs====== =========s ==== ses===========================
C05.001.001- IPC51-01 08/21/92 CLR _ N G05.001.002 IPC51-BEND-AA 08/21/92 CLR _ N C05.001.003 'ItC51-02 08/21/92 CLR _ N G05.001,004 11C51-03 '08/21/92 CLR _ N G05.001.005 ItC42-01 08/21/92' CLR _ N G05.001.006 ltC42-BEND-AA 08/21/92 CLR _ N ~' G05.001.007 ltC42-08 08/21/92 CLR _- N G05.001.008 ItC42-BEND-BS 08/21/92 CLR _ N G05.001.009 INC82-01 08/21/92 CLR _ N G05.001.010 ItC82-BEND-AA 08/21/92 CLR _- N G05.001.011 1tC-82-08 08/21/92 CLR _ N C05.001.012 1PC82-BEND-BB 08/21/92 CLR _ H G05.001.013 17C43-11 08/21/92 CLR _ H G05.001.014 -ItC43-BEto-CC1 '08/21/92 CLR _ N G05.001.015 'ItC43-12 08/21/92' CLR _ H
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FILE: ccro713%'JSIO4 QUALITY ASSURANCE CEPARTME DATE 12/I8/92 '- / PLAtiTs CATtJCA tHIT I PRE-SERVICE AND IN-SERVICE ItCPECTIO4 SYSTEM KEY: ITEM IU SER GC5 CATAHBA 1 INSERVICE ItCPECTICN Rest 1LTS OUTAGE 6 ItCOECTIct. INSPECTI24 IPCPECTIG4 GE U. ITEM PAESER ID tJUMBER DATE STATUS LIMITED REF. CCtfENTS
=========== s==========sssez=rms mz=smssazz =sss==zzzz =====ce=== ==== s==========nems==============s G05.001.016 1NC43-BEtc-CC2 08/21/92 CLR _
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' 5.0 flass'1'Insp3ction Resylts Examinations were performed during' Outage 6 on the Reactor Vessel, Pressurizer,-Steam Generators IA, 18,-IC and-10, Piping Welds of Upper.
liead Injection, Reactor Coolant (NC) and Safety injection (NI) Systems. Examinations were also performed on Reactor-Coolant Pump 1A, IB,1C and ID, Valves and Supports. 5.1 ReAc_ tar __Vr_siel Three (3) Reactor Vessel Control Rod Drive Housing Welds received a dye penetrant examination. -No reportable indications were_found.- 5.2 Pressurize.t Three (3) Pressurizer Nozzle to Safe-End butt welds. received a dye penetrant examination. No reportable indications were found. 5.3 . Steam 3G aerators Steam Generator 1A Channel Head to Tubesheet Weld received an ultrasonic examination. No reportable indications were found. 5.4 -Ptoina
.; -Dissimilar-Metal Butt Welds:
Four (4) dissimilar metal butt welds on the UHI Upper to l.ower Adapter, nominal pipo size 4 inches and greater received an ultrasonic and a dye penetrant examination. No reportable indications were found. j Similar Metal Butt Welds: Twenty-four (24) circumferential welds, nominal pipe size four inches and greater received an ultrasonic and a dye-penetrant examination. No-reportable indications were found. Four (4) circumferential welds, nominal pipe size-less than fdur inches,
. received a dye penetrant examination. No reportable indications were found.
5.5 fampsnent Suonorts !- Thirty (30) Class 1 Component Supports received a visual = examination as: required by ASME Section XI, Article-IWF-2500-1. No reportable conditions-were found. 5.6 Steam Generator Tubina a The Inconel 600 tubing in the four. Westinghouse Model 03 recirculating. steam generators (RSG's) A, B, C and D at Duke. Power Company's Catawba l j Unit I were examined by eddy current techniques during July / August / September 1992. The tubing-in the generators measures 0.750" nominal EQA408 Page.-1 L~ Revision 0 December 9,;1992-
~
outside diameter x 0.043" nominal wall thickness. The examinations were ! performed by personnel from Duke Power Company, B&W Nuclear Services I (BWNS) Company, Westinghouse, and Zetec, Inc., during the 6th refueling outage. One hundred percent (100%) of all tubes were inspected full-length with magnetic bias bobbin coil probes. One hundred percent (100%) of all tubes were also inspected at the inlet and outlet tubesheet secondary face with Zetec's SM-15 Motorized Rotating Pancake Coil (MRPC), Other areas of interest were also examined with an MRPC probe. Sleeved portions of tubes were evaluated using a combination of bobbin coil and rotating crosswound techniques. The following is a summary of the results of the bobbin coil, MRPC, and rotating crosswound eddy current examinations for each generator RSfuAl Eddy Current Examinations began in RSG A on 7/24/92 and were completed on 8/24/92. 4,554 tubes were examined full length by bobbin coil; 27 tubes contained indications 40% thru-wall (TW) or greater; 31 tubes contained indications 20-39% TW. 4,528 hotleg tubesheets and 4,554 coldleg tubesheets were examined with SM-15; 476 hotleg tubes, 444 coldleg tubes, and 221 U-Bends were examined using MRPC. 37 hotleg (HL) and 54 coldleg (CL) rolled plugs were examined using MRPC. 26 sleeves were examined using Rotating Crosswound. 86 tubes were removed from service by plugging. 8bSt Bl Eddy Current Examinations began in RSG B on 7/23/92 and were completed on 8/24/92. 4,630 tubes were examined full length by bobbin coll; 7 tubes contained indications 40% TW or greater; 14 tubes contained indications 20-39% TW. 4,630 botleg and coldleg tubesheets were examined by SM-15; 665 hotleg tubes, 572 coldleg tubes, and 220 U-Bends were examined using MRPC. 27'hotleg and 34 coldleg rolled plugs were examined using MRPC. 29 tubes were removed from service by plugging. EQA408 Page 2 Revision 0 December 9, 1992
-- RSG C:
1~1~ -- Eddy Current. Examinations began in RSG C.on 7/23/92.a'nd were-completed on 9/01/92. 4,480 tubes were examined full length by.' bobbin coil; 22 tubes contained indications 40% TW or greater;:25. tubes contained: indication 20-39% TW. 4,480 hotleg and coldleg tubesheets were examined by SM-15; l1,125 hotleg tubes, 650_coldleg tubes, and 221 U-bends were examined-using MRPC. 142 hotleg and 155-coldleg rolled plugs were examined using MRPC. 48 tubes were repaired by sleeving; 85 tubes were removed from= service by plugging. RSG D: Eddy Current Examinations began in RSG D on 7/24/92 and were completed on 9/5/92. 4,541 tubes were examined full length by bobbin coil; 43 tubes
-contained indications 40% TW or greater; 9 tubes contained -
indications 20-39% TW. 4,492 hotleg tubosheets and 4,541 coldleg tubesheets were examined by SM-15; 1,172 hotleg tubes, 352 coldleg tubes, and 218 U-Bends were examined'using MRPC. 72 hotleg and 89 coldleg rolled plugs were examined-using MRPC.- 49 sleeves were examined using rotating'crosswound. 60 tubes were repaired by sleeving;" 54 were removed from-service by. plugging. 5.7' hap _1 Twenty-four (24) Main Flange Bolts.on: Reactor Ceolant Pump 1C-received' an ultrasonic examination. No reportable 1.ndications were found. Reactor Coolant-Pumps 1A, 1B, IC-and 10, Flange S'urface and Reactor Coolant Pump 1C Seal Gland Bolts and-Seal-Housing Bolts received visual examinations. No reportable conditions were found. O EQA408- Page 3 Revision 0 December 9,'1992.
j '- .5.8 = lalyn [A
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Twelve l-(12) Studs and Nuts on Valves thC-1, -1NC and INC-3 received a--
'visualiexamination. -No reportable conditions were found.
Valve body weld on Valve INC-27 received an ultrasonic examinationi No reportable indications were-found. 1 The internal surface of valves INC-27 and IN1-129' received a' visual-- i examination.- No reportable conditions were found,- - j 5.9 Sylt.ef_n Leakage Test -
]
The Class 1 Pressure Boundary was subjected to a-system leakage test as- - required by ASME Section XI, Article IWB-5000. No reportable conditions ! were found. 5.10 Class 1 Repairs and Replacements i Repairs-and replacements for work performed-from June' 10,'1991-to October 15, 1992 are itemized in Section 11'of this report.
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l EQA408:- Page 4 Revision 0 f December 9,;1992-h
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**** B&W 4/91 EC FIELD EYSTEM (1M) (VER. 3.1) "" Tuesday Septenber 22, 1992 4:01 AM "" BABCOCK & WILCox Co. "uti Page 1
' [Ont Catawtie Unit 1 Steam Generator A ltge 7/92 RF0 fdV-it UUERT: B00BIH Colt INDICATIONS 40 100% TWD TEST R0W COL IND %TW VOLTS CHN DEC LOCAfl0N EXTENT LEG 1 APE ANLSI PRB COMMENTS
.......... ... ... ..+ ... ..... ... ... ........................ ........ ....... .... ..... ... . .... .. ~*
RES B00 1 67 IDI 40 8.24 P 1 9 TE HI + 15.07 91H TSP TE-HL- 79 - $1603 590 RES B08 2 .89 IDI 40- 2.91 P 1 75 TE HL + 18.48 91H TSP 1E-HL. 79 $1603 590 > RES BOB 4 94 101 40 16.80 P 1 25 TE HL + 7.22 97H ISP TE.HL 64 57752 610 RES B00 5 40 IDI 40 5.76 P 1 17 TE HL +-11.72 91H TSP TE HL 52 N6550 610-RES B00 5 42 IDI 40 7.93 P 1 15 TE HL + 6.21 9TH ISP TE-HL 52 N6550 610 - RES BOB 5 69 IDI 40 2.91 P 1 93 TE HL + 12.98 9TH TSP TE HL- 74 D4503 610-RES BOB IDI 40 7.12 P 1 32 TE HL + 7.93- 97H TSP TE HL ' 74 D4503 610' RES BOB 6 51 IDI .40 22.49 P 1 0 TTS HL + 0.00 91H TSP TE HL 57 88589 610 RES BOS 6 94 IDI 40 6.78 P 1 28 TE HL + 10.66 91H ISP TE HL 64 $7752 610 RES BOB 8 22 001 78 0.80 P 5 66 3RD TSP - 0.09 97H TSP 1E HL 44 E2505 610-RES BOS 8 68 IDI 40 3.24 P 1 28 TE HL + 11.95 91H ISP IE ML 74 D4503 610 RES B00 10 40 101 40 1.97 P 1 35 TE-HL + 8.22 91H ISP TE HL - 52 N6550 610 RES BOB 15 87 IDI 40 2.81 P 1 114 TE HL + 1?.26 97H TSP TE-HL 67 $1603 610 RES B00 18 67 001 69 0.18 P 5 78 2ND TSP + 0.50 91H TSP -TE HL 75 L7871 610 RES BOB 20 78 IDI 40 9.29 P 1 18 TE HL + 13.78 91H TSP TE ML 70 $1603 610 RES BOB 21' 58 IDI 40 3.36 P 1 41 TE-HL + 14.41 97H ISP TE HL 78 M1384 610 RES BOB 23 58 IDI 40 3.26 P 1 40 IE ML + 9.31 91H ISP TE HL 78 M1384 610 RES BOB 27 45 IDI 40 20.06 P 1 22 TE HL + 16.04 91H TSP TE ML 54 D3162 610 RES BOB 30 100 101 40 2.21 P 1 23 TE*HL -+ 9.44 97H TSP TE HL 62 H7791 610 RES B00 33 55 101 40 2.57 P 1 38 TE-HL + 9.00 91H TSP TE HL 58 F3453 610 RES BOB 36 70 ID: 40 16.48 P 1 20 T[*HL + 4.27 9TH TSP -TE HL 74 16956 610
.RES B00 38 47 IDI 40 1.30 P 1 79 TE HL + 3.30 91H TSP 1E HL 55 F3453 610 RES BOB' 39 44 IDI. 40 1.98 P 1 48 TE HL + 4.96 9TH ISP TE HL 54 D3162 610 RES B00 39 84 IDI 40 4.03 P 1 23 TE-HL + 4.48 97H ISP .TE-HL 68 F3453 610 RES B00- 47 47 IDI 40 1.28 P 1 67 TE*HL + 3.25 97H TSP TE HL $5 'F3453 610 RES B08 48. 54 WAR 40 3.54 P 2 0 17TH TSP + 0.00 9TH TSP TE CL 15 J1978 630-RES BOB 48 66 WAR 4f 4.39 P 2 0 17TH TSP + 0.00 9TH TSP TE CL 29 D4576 630 RES BOB 49 57 WA 41 3.91 P 2 0 151H TSP + 0.00 91H TSP TE CL 16 G6495 630
-a 27 k O TOTAL TOTALTUBES IWolCAfl0NSFOUND FOUND e 28
) TOTAL TUBES IH INPUT FILE = 4674 O
.o. . .. '**** B*W 4/91 EC FIELD SYSTEM (TM) (VER. 3.1) **** Tuesday Septewber 22, 1992 $t21 AM **** BADCOCK E WILCOX Co. ****It Page 1
- /
' Svit' Age Cata e7/92 Unit RTO 1 Steam Generator 8 i /
BOBBIN C0ll INDlEAil0NS 40 100% tuD
'1\ ".UJERY:
'%i R0W COL IND %1W VOLIS CHN DEG LDCATION EXTENT (EG 1 APE ANL$1 PRS COMMENTS Rs 3 17 ODI 48 0.13 3 101 $iN TSP + 7.03 91H ISP- TE HL 27 P2201 610 reb , 11 21 001 40 8.35 P 1 22 it-HL + 14.36 9TH.1SP IE*HL 29. D8021 610
'RES BL 11 27 101 40 9.65 P 1 30 TE HL + 16.19 91H ISP IE*HL 31 C3556 610 RES BOB % 11 IDI 40 8.11 P 1 16 IE HL
- 16.37 91H TSP TE HL 25 ED864 610 RES 800 14 101 40'12.49 P 1 23 IE HL + 12.51 91H ISP 1[*HL . 34 M0155 610 RES BOB "l 40 1.17 P 1 52 TE HL 4 9.02 9TH TSP 1[ HL 17 HBS$1 610 RES BOB 2 ' 40 0.93 P 1 45 TE HL + 17.11 91H ISP TE-HL - 34 57752 610 TOT AL TU8ES fus a 7 TOTAL INDICAfitNa 40 m 7 TOTAL IUBES IN INPL. ILE = 4674 31 w
i
)
J - *** B&W 4/91 EC flELD SYSTEM (TM) (VER. 3.1) **** Ivesday September 22, 1992 5:12 AM **** BABCDCC & WILCOX CO. ****l1 Page 1 4 >
- vit a Stearn Cerwrator C 7/92 RF0
~..[ ^/ %ge Cata.de Unit 1' - t #
. % 2 RT: B0061N C0!L INDICATIONS 40100% TWD TEST- RDW COL IND X1W VOLTS CHN DEG LOCAlloW EXTENT. LEG TAPE ANtSI PRd COHMENTS~
RES B00. 4 92 ODI 49 1.13 P 5 95 2ND TSP
- 0.06 9TH TSP TE.HL 48 L7871 610-RES BOB 4'107 ODI 87- 1.03 P 5 53 3RD ISP + 0.00 91H TSP TE.HL 21 H3464 610 RES 808- 11 82 IDI 40 3.45 P 1 156 TE HL + 17.09 91H ISP TE HL- 30 K7060 610 RES BOU 11 106 IDI 40 15.62 P 1 15 TE HL + 14.13 91H TSP TE HL 49 M1384 610 .
RES BOB 12 til 001 100 3.44 P 5 37 2ND TSP + 0.00 9tH ISP TE HL 21 W9213 610 RES Boa- 13 18 001 43 0.40 P 5 101 3RD ISP - 0.05 9TH TSP TE ML 6 D1756 610 RES B00 13 89 IDI 40 4.07 P 1 150 TE HL- + 5.25 91H TSP TE*HL 27- 03162 610 RES BOB 14 86 101 40 2.08 P 1 145 TE HL + 17.07 91H TSP TE-HL 28 08021 610 RES Boe 15 109 001 100 1.57 P $ 37 3RD TSP
- 0.05 91H TSP TE-HL 21 H3464 610 RES Boe. 17 58 101 40 3.69 P 1 151 IE*HL + 13.55 91H ISP TE HL 41 H4495 610-RES B08 IDI 40 2.34 P 1 87 TE HL + 8.51 91H TSP TE HL - 41 H4495 610 RES B00 19 48 IDI 40 12.09 P 1 22 TE*HL + 15.95 91H ISP TE HL 17 H7791 610 RES COB 19 1D6 IDI 40 2.63 P 1 51 TE CL + 20.12 9TH ISP TE CL 69 D4503 630 RES B00 20 48 IDI 40 3.11 P 3 70 TE*HL + 12.14 91H ISP IE HL 17 D4576 610 RES BOS- 23 48 IDI 40 3.63 P 1 32 TE HL + 14.03 97H ISP TE HL 17 M7006 610 RES Bon 23 77 IDI .40 5.39 P 1 12 TE HL + 15.23 91H ISP TE HL 32 M6078 610 kES Bou 23 103 IDI 40 16.08 P 1 8 TE HL + 11.50 97H TSP TE ML 22 S1603 610 RES Boo 25 77 101 40 13.67 P 1 18 TE HL + 12.55 9tH TSP .1E HL- 32 M6078 610 RES B00 101 71 12.67 P 1 40 TE HL + 8.64 9TH TSP TE HL 32 M6078 610 RES Boo 25 78 101 40 10.65 P 1 13-TE HL + 15.15- 9TH ISP TE*HL 32 C3340 610 -
RES Boa 27 90 IDI 40 7.84 P 1 15 TE HL + 7.42 91H TSP IE.HL 27 B7702 610 RES BOS 31 103 101 40 3.60 P 1 166 TE HL + 15.69 91H ISP TE HL 22 51603 610 RES Ben 44 40 001 81 0.68 3 59 4AVD + 8.18 9TH TSP TE HL 2 F3453 610 RES Boo 49 73 IDI 40 15.67 P 1 20 TE*HL + 10.25 9TH TSP TE HL 34 $1603 610 TOTAL TUBES FUUND e 22 TOTAL INDICATIONS FOUND e 24 TOTAL TUBES IW INPUT FILE o 4674 11 ( ou
e
- **** B&W 4/91 (C FIELD SYSTEM (TM) (VER, 3.1) '" funday September 22, 1992 7513 AM * *" BABCOCK & WILCOX CO. ****11 Pa'ge 1-
' Mant Steam Generator 0.
[ jge: Catawba Onft 7/92 RF01 31 RY: BOBBIN C0ll INDICAil0NS 40-100% TWD 1E$i ROW COL IND %IV VOLIS CHN DEG LOCAlloN Exi[Ni LEG 1 APE AhtSi PRS COMMENTS RCS B08. 1 - 20 101 40 13.96 P 1 14 IE HL + 11.55 91H ISP TE HL 81 .88090 590 RES BOB 2 40 00l' 40 5.84 P 1 12 TE HL + 8.18 91H TSP TE HL 81 K7060 590 RES BOB. 2 112 IDI 40 1.82 P 1 83 TE HL + 12.33 91H TSP TE HL 80 W1424 590 RES B08 4 26 101 40 6.64 P 1 18 TE HL + 6.22 91H TSP TE HL 65 59098 610 RES 908 4 40 101 40 7.35 P 1 11 TE HL + 15.70 8IH ISP. 1E ML 81 R$555 590
-RES BO8 4 82 001 91 0.25 P 5 45 3RD TSP + 0.05 91H TSP TE HL 48 G4943 610 RES BOB 5 58 IDI 40 9.01 P 1 9 IE HL + 9.16 91H ISP TE HL 80 W1424 590 RES B08 6 3 col 49 1.18 P 5 95 2ND TSP + 0.16 91H ISP. TE-HL - 58 E2505 610 RCS BGB 6 6 IDI 40 9.00 P 1 24 TE HL + 6.26 9iH TSP IE+HL 59 88090 610
.RES BOB 6 9 001 75 1.07 P 5 67 3RD TSP + 0.00 9tH TSP TE HL 83 W9213 590 RES BOB 6 51 101 40 9.03 P 1 24 TE ML + 15.34 91H TSP TE HL 77 F9284 610 RES B08 6 95 IDI 40 2.40 P 1 24 TE HL + 14.94 9tH TSP. 1[ HL 43. M1384 610 RES B08 7 7 ml 67 1.28 P 5 79 2ND ISP + 0.02 97H TSP TE HL $9 F3453 610 RES Boa 7 - 72 Col 61 0.81 P 5 90 3RD TSP + 0.00 9fM TSP- TE-HL 53 W9213 610 RES EOS 8 75 EDI 83 1.09 P 5 63 3RD TSP + 0.00 9IH ISP TE HL. 50 J1978 610.
RES 808 8 96 101 40 4.66 P 1 13 TE*HL + 8.99 91H TSP TE*HL 43 M1384 610 RES BOB 9 79 ODI 51 1.09 P 5 93 2ND iSP + 0.08 91H ISP TE HL 69 M7006 610 Ris BOS 12 108 001 86 2.20 P 5 58 2ND iSP - 0.10 91H ISP IE HL 39 J1978 610-RES B08 16 79 101 40 9.39 P 1 19 TE-HL + 14.36 91H TSP TE HL -49 W1424 610 KES BOB 17 65 IDI 40 9.53 P 1 18 TE l:L + 11.91 91H !$P TE HL 55 F6623 610 RES BOB 17 73 IDI 40 9.02 P 1 18 IE HL + 10.58 , 91H TSP TE HL $2 W9213 610 RES B08 101 40 24.51 P 1 33 TE HL- + 12.43 91H TSP TE HL 52 W9213 610 RES BOB 17 81 IDI 40 11,75 P 1 29 TE HL + 17.39 9iH TSP TE*HL 48 M3442 610 RES BOS 17 110 101 40 2.11 P 1 32 TE HL + 6.30 91H TSP TE HL 39 D1756 610 RES BOB 18 70 101 40 7.70 P 1 15 TE HL + 12.26 9TH ISP TE HL 53 H7791 610 RES BOB 19 74 101 40 4.59 P 1 16.TE*ML + 3.54 91H ISP TE-HL 52 W1424 610 RES B08- IDI 40 3.%d P 1 15 TE-HL + 2.49. 91H TSP TE HL- 52 W1424 610 RES B08 20 30 IDI 40 2.45 P 155 TE HL + 11.28 91H ISP TE-HL 67 $2748 610 RES 808 20 108 IDI 40 2.73 P 1 31 TE-HL + 3.31 9fH TSP TE HL 39 F3453 610
*ES Boo 21 34 IDI 40 5.06 P 1 151 TE HL + 15.14 97H TSP TE-HL 69 W1424 610
$ 22 74 IDI 40 13.00 P 1 26 TE*ML + 4.78 91H ISP TE HL 52 W1424 610-
; 25 107 001 50 3.01 3 101 181H TSP + 1.12 9TH TSP TE CL- 2 R1509 630 b+} B08 t
% 5 BOB BOB31 90 001 53 0.17 BOB 27 36 IDI 40- 8.11 P 5 15 TE-HL + 17.20 3 94 71H ISP + 42.49 91H TCP TE HL 91H TSP TE HL 70 $9098 610 45 F3453 610 RES B08 37 60 IDI 40 8.00 P 1 10 TE-ML + 12.53 91H ISP TE-HL 83 $8046 610 ,
RES BOB 37 68 IDI 40 1.41 P 1 40 TE HL + 9.20 10iH ISP TE HL 54-i.6550 610 RES BOB 38 45 001 68- 1.35 P 5 80 2ND TSP
- 0.05 9TH TSP TE-HL 74 $7752 610 RES 208 41 68 IDI 40 1.87 P 1 35 TE HL + 17.97 91H TSP TE HL 54 N6550 610 -
RES BOB 41 89 101 40 1.32 P 1 53 TE-HL + 4.76 91H TSP TE-HL 46 F3453 610 RES B0d 42 28 IDI 40 2.59 P 1 13 TE HL + 20.31 91H TSP TE-HL 66 M3442 610 RES BOB 43 34 001 82 1.02 P 5 66 2ND TSP - 0.04 9fH TSP TE*HL 68 F3453 610
-RES B0B 47 28 IDI 40 1,43 P 1 131 TE-HL + 10.09 91H TSP TE-HL 66 M3442 610 RES 808 47 49 IDI 40 5.13 P 1 1T TE-HL + 6.31 91H TSP TE*HL 86 W1424 590 RES BOB 47 86 IDI 40 2.46 P 1 38 TE*HL + 12.24 91H ISP TE*HL 46 E2505 610 RES 808 48 42 IDI 40 6.60 P 1 16 TE-HL + 12.36 101H ISP TE*HL 72 W1424 610 TOTAL TUBES FOUND = '43 TOTAL INDICATIONS FQlWO e 45 TOTAL TUBES IN INPUT FILE = 4674
>L L - (U .
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F-
'6.0 Class 2 Inipu lion Results Inspections were performed during Outage 6 on RHR_ Heat-Exchanger 1A, ..
Steam Generators 18 and 10, piping integrally-welded attachments on Main feedwater (CF) System and on Piping Welds of Auxiliary Feedwater (CA), Main Steam. Supply to Auxiliary Equipment (SA), Main Steam.(SM), Main Steam Vent to Atmosphere (SV), Main Feedwater-(CF) and Safety Injection (NI)~ Systems. Examinations were also performed on . Component- Supports. 6.1 Eqiidual Heat _ Removal teat Exchanger and Steam Generators _ - Residual Heat Removal Heat Exchanger IA Inlet Nozzle A and Reinforcing Pads, Outlet Nozzle B and Reinforcing Pads to Shell Welds-received-a dye penetrant examination.per Problem Investigation report.'#0-C91-0439. No reportable indications were found. Steam Generator 18 Main Steam Nozzle _to Upper. Head Weld and Steam-Generator 10 Auxiliary Feedwater Nozzle to Shell Weld received a magnetic particle examination per problem Investigation Report #0-C91-0439. No reportable indications were found. A copy of Problem Investigation Report #0-C91-0439 is included in-Section 10 of this report. 6.2 Pipina Welds one-half' inch and less nominal wall thickness: Twenty-six (26) circumferential welds and one-(1) longitudinal weld received a magnetic particle examination. No reportable indications were found. Welds greater than one-half inch nominal wall thickness: Twelve (12) circumferential welds received an ultrasonic and a magnetic-particle examination. Thirteen-(13) circumferential welds received an ultrasonic and a dye penetrant examination. Three (3) circumferential welds received a_ radiographic and a, magnetic-particle examination. ..No - reportable indications were found. Piping Integrally-Welded A+.tachments: Three (3) integrally-welded attachments __on Main- Feedwater (CF) System received a magnetic particle examination. No reportable indications were found. 6.3 Comoonent Sunoorts Sixty-onel(61) Class 2 Component Supports received visual examination as required by ASME Section XI, Article"IWF-2000. -No reportable conditions , were found. EQA408 -Page 1 .. Revision 0 December 9, 1992
V' '
-i-g.: _ 6.4 System or Component-Functional Tesk ,
i
,~
4 Class 2 Functional- Tests.were performed as- required by ASME SectionLXI,-. Article IWC-5000; .No-reportable conditions were found. t- -6.5 - Classj2 Repairs and Replacem_ents. Repairs and _ replacements for work performed from June 10, 1991' to f October 15, 1992 are itemized in Sectioni11 of this: report. p . l
.V
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8 7 J m EQA408 Page.2-Revision 0~ December'9,.1992 T
--1.
7.0 Augmtgiqd_lmpecilgn_Jeiulli Augmented inspections were performed on Reactor Coolant Pump Flywheels, Steam Generator Preheater Sections, Main Steam System for Pipe Rupture Protection and on Thermal Stress Piping (NRC Bulletin 88-08). 7.1 ReAC.lar_Caolanilymp_Ely_ wheels Reactor Coolant Pump 1A Flywheel received an ultrasonic examination. Reactor Coolant Pump 1B Flywheel received an ultrasonic and a magnetic particle examination. No reportable indications were found. 7.2 Sigam_DRn_erator Tutte Pr.shtaler_Sef; tion All four steam generators were examined by eddy current methods. Results and evaluation data for examinations are shown in the Catawba Unit 1 July 1992 Refueling Outage Eddy Current Examination Report. 7.3 Eip.e_Ruoture Pro _ittilgn Eleven (11) welds on the Main Steam (SM) System received an ultrasonic and a magnetic particle examination. No reportable indications were found. 7.4 IharmA1_ Stress Pinina ( Nine (9) welds and seven (7) bends were examined by ultrasonics on Reactor Coolant (NC) System, as required by USNRC Bulletin 88-08. No reportable indications were found.
'O EQA408 Page 1 Revision 0 1 l
December 9, 1992
8.0 h.tsonneblquinnera _ansLHelerial CertillCAtloni q iO All personnel who performed or evaluated results of inservice inspec-tions f rom June 10, 1991 to October 15, 1992 at Catawba 1 were certified in accordance with the requirements of 1980 ASME Section XI with Addenda through Winter 1981. The appropriate certification records for each Duke Power Company inspector and periodic calibration records for Duke Power Company inspection equipment are on file at Catawba Nuclear Station or in the Corporate offices in Charlotte, North Carolina. Records of periodic calibration of Duke Power Company inspection equipment are on file at Catawba Nuclear Station or in the Corporate Office in Charlotte, North Carolina. 8.I hr19nnEL1Ru1Rm.ent and MateriallettificaMons - Eddylurrent lestins See Duke Power Company " Eddy Current Examination Report Catawba Unit 1 July 199?. Refueling Outage" on file at the Corporate Office in Charlotte, North Carolina. O O EQA408 Page 1 Revision 0 December 9,1992
f
.s '9.0 -Problem InvestiaA. tion Renorts--
(g A. copy: of each Problem Investigation Report. resulting:-from- reportable ~ .- items,; originated lagainst; scheduled inservice. inspections performed
'during Outage 6,-is included in this.section. All were_ resolved:and'
-found acceptable before returning-Unit.1 to service.--The:following Problem Investigation Reports were issued P.I.R HO. Deic>tjipli_qn Date_ Issued None 4
i 1 (@ . 1 L yg L - EQMOS .Page.1 Revision-0 December 9,fl992 e- - 7 ,,, , , .g y ,..r,.. 9
. 4
- I i ;
; -- < _ 10.'0LReferenceDocuments - -,
The~following: reference _ documents apply to the inservice inspect _ ion-- - ! _ performed during Outage-6(at Catawba 1:~ ,
- Duke Power Company Problem InvestigationI.;Repot.t 2
0-C91-0439-
- Duke Power Company Technical Documentation.#90-1_ dated March 6, 1990;- 1 f
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December 9l--1992 - ' ~
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v)' PROBLEM INVESTIGATION PROCESS PROBLEM IDENTIFICATION FORM .
I. Problem investigatioru (See Attached) 0:cwred-Tune /Dase: Discovered Tune /Dese Unit (s) Unit (s) Steams et Tune ProMen Occuned: I restinno(ProMen: DiacriptionnedCauseofthePitMeau -
. T===diaa=Conective ActicesTakes/ToBeTaken:
other Unis(s) ANected: ( ) Yes ( ) No ' Probleen id==ei A=+ Date Section by IL Signi5cencee (See. Attached)
. (4 Event Code Inidel Cause Code (s) 1. 3.
- Sedal Nanber .
- 2. 4.
1 Is.this probleen miraiw ( ) Yes ( ) No . (-) Delete Rasponsible Sectice(s) 1. 2. 3. 4. Screened By: Date:- Ot!T*BUT3006:
* * -J o .9 s .
AM -',' WOldan M O M tti M*ahh tdk4edelle E"Alf*E_Lle M l'eclarA u3 c,,;tc. c LKcA4 (d Rt'c N Rf. m rw TP h an tRNo i FDfAL 0000DfATOE
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6Wien fefrY (([ CATAWBA NUCLEAR STATION PROBLEM INVESTIGATION PROCESS PROBLEM IDENTIFICATION FORM I. Problem ID Occurrod Timo/Date UNKN / / Disc Timo/Dato 09/30/91 Unit (s) O Status at Time Occurred U1M1,U2EOC4 Location of Problem CNS D:scription & Cause: As a result of ONS PIR 4-091-0093, a data review of-the Catawba Nozzle - to V asel Wolds revealed that the following item numbers woro insp:cted using tho' incorrect acceptance standard Unit 1 CO2.011.001,CO2.011.002,CO2.021.004A, and CO2.021.012A, Unit 2 CO2.011-001,CO2.011.002 and CO2.021.051A Immediate Corrective Actions: ThO correct Unit 2 inspections are being dono at 2EOC4 ( m Identiflod By: RNGILES Date 11/18/91 Section NON ArbNbhorUnitsAffected? (Y/N) N II. Significanco Event Codo Initici Cause Code (s): Alb- D1 S rial Number 91NON0177 R00ponsible Section(s): QA Scrocned By: GBROBINS Date 11/19/91 Is the problem significant?Y v l
l l COMPLIANCE EVALUATION FORNe s (
. PROBLEM INVESTIGATION REPORT SERIAL NO.: 8-2f/ 4 87 LICENSB EVENT RET 0RT NO.: SA1/7/. J7 -
C9'/ -677' o. 31 4 %1b on er$ Ill. COMPLIANCE EVALUATION Opersbdity Review By: b Daae: //- I f' f / System /Componeet Operable: (vi Yes ( ) No ( ) Not Appucable Com===w k sak nJm e) +a kJ m vt sQJo rwed) W gdub.
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---------------- --------------------------------==--------- --
Reportability Determinados By; b# s Date: //- IT 9/ Problema Reportable: (vf Yes ( ) No - Reportable Per: /e . C'S :.-" 7.:?(-)^)f) 5 .i A-18 "' Co==-mas ,Q $:== AL - h- n a r-r a(L a _,. 2 L 21 L n da g c =
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, 7 .r - ._,. - - - - - - - - - - - - - - - .
Nodfation Made (If Raportable to NRC) Time /Date: v4- /' v/ NRC C&- , /A- DPC Contractor: W Date Notifwd: NRC Res. Inspector: # Statica Manager: A/d' Nuclear Support Duty Engineer: di-
------ ------------ . - --- ----- ===- -----------------------
Investigation AssignedTo:
- r+XC Doo Dese:' M Date Due to Complianos After Evaluatica: /*//2 *f/
Reportable Event FIR Review: ~ b Date: /.A. /8 /
' Cof=p3- Manager / I
----- ==--- ---- ------- --------- ---- ----------- -- ---.
Upper Tier Eval =tian Assigned To: M-Commanw
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----==-- - . . . . -- ---- -------- ----- ---- -------..
O i
Catawba Nuclear Station _ Regulatory compliance
, PIR File
( u-l December 18, 1991 MEMO TO FILE
SUBJECT:
Catawba Nuclear Station Station-Report - IIR C91-087-0) PIR 0-C91-0439 File No: C11-815.04 . The attached report is being submitted as a S'tation Report concerning USE OF INCORRECT ACCEPTANCE STANDARDS DURING WELD INSPECTIONS DUE TO DEFECTIVE PROCEDURES. (b o . VW//h Wd W. R. McCollum, St Ift3anager Catawba Nuclear Sta ,on kon: STATION.RPT xc G. B. Robinson J. W. Glenn S. T. Rose IIR C91-087-0 + q L)
DUTI POWER COMPAfiY CATAWBA fiUCLEAR STATION (f PROBLEM IlfVESTIGATIOff REPORT 110: 0-C91-0439 USE OF I!JCORRECT ACCEPTANCE STA!4DARDS DURING WELD IllSPECTIollS DUE TO DEFECTIVE PROCEDURES ABSTRACT on llovonbor 18, 1991, Unit 1 was operating in Hodo 1, power Operation, and Unit 2 was in refueling outago 2EOC4. A station Quality Assuranco (QA) Specialist was reviewing wold inspection data, due to problema discovered i with wold data at the Oconoo Nuclear Station, when it was determined that the wrong acceptanco standards had also boon applied to the Catawba inspections. Under Technical-Specification 3/4.0, Limiting Conditions For Operation And Surveillanco Requiremonto, in-sorvice inspection and testing i of ASKE Codo Class 1, 2, and 3 oquipment shall be performed in accordance with the ASME code, or as specified by lluclear Regulatory Connission + requiromonts.. Inadvertently, the proceduros directing the weld exams allowed application of less stringent acceptance critoria. A review of
' wold inspection data revealed that no flaw indications were present on the subject wolds. Regardless of the applied acceptanco critoria, inspectors record any relevant flaw indications on the weld inspection data sheets.
This ovent has been attributed to Dofoctive procedures. The applicable Unit 2 wolos have been re-inspected with satisfactory results. The l ( remaining Unit 1 wolds will be re-inspected during 1EOC6. Appropriato inspection proceduros waro revised with future revisions pending. Training l i on the procedura changes will be ptovided for the appropriate inspectors. This report is being submitted as a Station Report. l l 5
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y_ .. l PIR 0-C91-0439/ Station Report Pago 2 (!(V BACKGROUND Technical Spoeification (T/S) 4.0.5 requiros in-service inspection of ASME Codo class 1, 2, and 3 components and in-service testing of ASME Code Class 1, 2, and 3 pumps and valves to be performed in accordance with Soction XI of the ASME Boiler and Pressure Vossol Codo, and applicable Addenda, as required by 10CFR Part 50, Section 50.55a(g), except whero specific written relief has boon granted by the Comminaion. For the Duko postor ASME Section XI Han e l, Quality Assuranco (QA) in responsible for wold inspection activition. All inspections shall moet tho requirements of a ASME Section XI specified or as allowed in specific Codo casos or Rollof Roquests. Catawba's In-servico Inspection Plan utilizes
- the 1900 Edition of ASME Codo Section XI, with Addenda through Wintor 1981.
Examination Categorloo for nozzlo to vosnol wolds are given in Tablo IWB-2500-1 of Section XI, Article IWB-2000. At least 16% of the nozzlo to vossol wolds chall bo examined by the end of the first inspection period (first 3 years of tho first 10 years of operation), and a minimum of 50% at
;( the end of the second period (yoara 4-7).
Tho General Offico (GO) QA ISI Specialist who oversees Catawba's ISI program unos the information obtained from ASME Section XI, and other sources, and works with the QA Catawba Sito ISI Coordinator to establish the timetables for all wolds that require in-servico inspection at' Catawba. The examination techniques used for in-service inspectiono include Radiographic (RT), Ultrasonic (UT), Magnetic particlo (MT), Liquid Ponetrant (PT), Eddy Current, and Visual examination methods. For all examinations, both remote and manual, specific precedures are prepared describing the equipment, inspection techniquo, oporator qualifications, calibration standards, flaw ovaluation, and records. Tho'In-service Inspection Plan for Unit 2 was submitted on August 10, 1986. The in-service insgection interval is overy 10 years (4 total). Detailed inopoetion listings and scheduling are contained within the Catawba In-servico Inspection Plan. The Non-Dostructive Examination proceduros (NDE-25 and NDE-35) states " For Clana 1 or Clasa 2 components where acceptance standards are not specified, one of the following acceptanco standards shall be used: (1) ASME Section III edition applicable to the construction. (2) ASME Section XI class 1, p (3) Tho original construction code (excludes NDE-35).
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- I Thu inspections involved with this b t aro; Residual Heat Homoval Heat i Exchanger (Rx) 1A/2A Inlet and Outlet Hozzles; Steam Generator ID Upper I Hain Stoam Nozzlo; Steam Gonorator ID Auxiliary Feodwater Hozzle To Shell; and the Safety Injoction Accumulator Tank 2D outlet Nozzlo.
EVENT DESCRIPTION, on September 9, 1991, an Oconee Nuclear Station (ONS) QA Specialist assigned to the Gonoral office was reviewing ISI data when it was discovered that a flaw indication recorded during an inspection was initially determined to be acceptable. The dimensions of the flaw were recorded on the inspection data shoot were compared to the inspection acceptance criteria. It was determined that,the flaw was actually una(ceptable. It was concluded that the wrong.acceptanco critoria had been appIind to the inspections that had boon performed. ONS Problem Investigation Report (PIR) 4-091w 193 was initiated. On November 1B, 1991, Catawba QA performed a review of their ISI data recoried for the nozzle to vessel wolds in response to the ONS PIR. This (O h rovietlRrevealed that the CHS inspections also employed the wrong acceptanco critoria. The three Unit 2 welds wore )e-inspected using the correct acceptance
, critoria between November 19th and 20th. No flaw indications excooded the acceptable limits of the inspections.
The Unit 1 ND Hx Wolds were inspected on November 27, 1991. No unacceptable indications were' discovered. The Unit 1 S/G 1B upper main steam nozzle and S/G ID CA weld inspections havo been scheduled for 1EOC6. CONCLUSION This incident is attributed to Defective Procedures because the procedures listed multiple acceptance criteria for the inspections. The initial nozzlo to vessel wold inspections were performed using the wrong acceptanco critoria becauso QA selected ASME Section XI acceptanco critoria for the inspections instead of the more stringent construction code standards. A subsequont review of the weld inspection data shoots revealed that no flaw indications were observed by'the inspectors. Wold inspectors record any flaw indications (> 1/16") regardless of the acceptance critoria limits applied to the inspection. Thorofore, it was determined that the wolds inspected under the subject circumstances are acceptable under the criteria , 'f -( established from the construction code.
PIR 0-C91-0439/ Station Report Page 4 co Due to the problem diccovered at ONS, NDE-25 and NDE-35 woro revised on Octobor 15, 1991, to requiro use of Appendix A (section 16.5.1 of NDE-25 and 13.4.1 of HDE-35) to specify acceptanco critoria whou acceptanco standards are not specified for Class I and II components, rurther revisions to NDE-25 and HDE-35 will add the requiremont for documentation of any rolovant indications regardless that the indication does not exceed the applied acceptanco critoria. CORRECTIVE ACTION SUBSEQUENT
- 1) The affected Unit 2 nozzlo to vessel wolds woro re-inspected using the propor.acceptanco critoria.
- 2) Unit 1 RHR Hx 1A nozzio to vossol wolds woro re-inspected using the proper accep.tanco critoria.
/ PLANNED k(
- 1) NDE-25 and NDE-35 will be revisod to require that all relevant indications excooding 1/16" will bo recorded .
- 2) QA inspectors will be trained on solecting acceptanco critoria for compononts that do not have specified standards.
- 3) Unit 1 S/G 1B Main Steam nozzlo to upper head wold will be ro-inspected using the proper acceptanco c'ritoria.
- 4) Unit 1 S/G 1D Auxiliary Foodwater nozzlo to shell wold will be to-inspected using the propor acceptanco critoria.
SAFETY ANALYSIS Ho flaw indications were detected during cubsequent roinspections using the correct acceptanco critoria. No adverso impact was inflicted upon the performance or operability of the systems affected by this incident. The health and safety of the public woro not affected by this incident. O
PIM U-Wi-UgJy/ btat10n M$ port l Paga 5 i 1 I I ENCLOSURE 8.1 Safety Review Group Signatures Prepared By: R. C. Rayfield Dates December 10, 1991 , Reviewed Dyt .h. d? Datet Oh* 91 ! N. . J dho t2, Dato /SL - /.'3 -N /
} Datet 12.Y/Z Yl
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dl6 $Ik Datet Approved By: A_ Datot / Z !/7/9/ Chairnian, CSRG ENCLOSURE 0.2 Listing Of Enclosures -
# Title 8.1 Safety Review Group Signatures 8.2 Listing of Enclosures 6.3 Cause Code Assignments 0.4 Corrective Action Schedule 0.5 References 8.6- Safety Review Group consideration of Part 21 Reportability 8.7 Personnel Referenced-
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ii b ENCLOSURE 0.3 C_ause code Ansignments Root Couno D1 Dofective Proceduro - Technical deficiency i ENCL-TURE 8.4 Correctivo Action Schedule
- Corrective Action # -Assigned To Don Date (Q 1 Quality Assurance 3/31/92 2 Quality Assurance 3/31/92 3 Quality Assurance 1EOC6 4 Quality Assurance 1EOC6 ENCLOSURE 0.5 References ONS PIR 4-091-0093 NDE-25 & IM -35 ASME Code Section XI O
k 1
nn u-w s~umt *Luuun n:Vort. PLg3 1 ( E!K10SURE 0.6 Safety Review Group Consideration of Part 21 Reportability l l Yon g I. lias a " Defect" or "Doviation" boon identified in a " Basic X Component"? II. Is the "Dofoct" or "Doviation" procent in a " Basic Component", that is a plant structure, system, component or part thoroof noconsary to ensure:
- 1. The intogrity of the reactor coolant boundary? X
- 2. The capability to shutdown reactor and maintain it in a cafo shutdown condition? _X_
- 3. The capability to provent or mitigate the (l( concoquences of accidents which could result in potential off-sito exposuro comparable to those referrod to in 10CFR100.117 X Including donign, inspection, tonting, or consulting norvicos related thoroto.
- III. Is the " Basic Component" one that has boon accepted for ownership or installed for uno or operation? X If a yos in I, II and III above, could defect croato a substantial safety hazard or contribute to excooding of X a safoty limit as defined in Toch Spoes?
1 Comments Prepared By: h. Dato /d*/%*9/
"af tl Rev w Group Reviewed By: L Dato: 12 "I 6 k N Compljunco
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,6%c I of l Proposed Resolution to PIR 4 091 0093 (l
All of the nonle to shell welds (ASME Section XI C B Wel6) for the second interval : Oconee Units 1,2, tnd 3 have been reviewed to determine h extent of this situation. This review revealed that this was not in i$ cue and the inconcet acceptance criteria was used for all nonle tom welds. The following corrective actions will be taken:
- Procedure NDE 25 will be revised to citiify when to use Appendix A vs the other ISI acceptance Appendices. As a result of this -
revision, trr.ining will be conducted for all Level 11 MT/PT Inspectors at Oconee. (During the process of lavestigating this altuation, it was identified that procedure NDE 35 is worded similar to NDE 25 and also will be revised for citriflettion), a
%e training progrtm will be revieUed by the NDE Level 111 g Examiner to ensure that the lesson plan adequately addresses how to go about selecdng the teceptance criterit in different situttlons, e
An Addends will be written t0 the ISI Plan t0 re schedule the nozzle to shell welds for re exuninttlen.
'Ite following is a list of the ASME Section XI Item Numbers assigned to -
~
the noule tolhell welds which were reviewed for this disposition: UNIT 1 UNIT 2 EU p$ CO2.010.001 C02.010.001 CO2.010.001 C C02.010.002 C02.010.002 C02.010.002 C02.010.003 C02.010.003 C02.010.003 C02.010.004 C02.010.'004 C02.010.004 CO2,021.001A C02.02i.001A C02.021.001A C02.021.002A C02.021.002A C02.021.002A C02.021.003A C02.021.003A C02.021,003A CO2.021.004 A CO2.021.004 A CO2.021.004A CO2.021.005 A CO2.021.005 A CO2.021.005 A CO2.021.006 A CO2.021.006 A CO2.021.006 A 1 -
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3* I lt A l'I'HO V AI, ~ LJ1tG FJfT PIR N 0-C91-0439 LER # STATION REPORT
Title:
Uno of Incorrect Acceptanco Standards Dur.ing Wld Inspection Duo To Defectivo Procoduren Author: R. c. Rayfield Ext.: ._5628 This PIR is being routed for approval. Please indicate your approval below. If you havo quantions or coninento, please contact the Stuart Roso (x3393) innwx11ately. INITIAI.S/DATE Reviewg Approvod Comments Comments Ronolved GBR [t M ' N I'Litants RICTUREE TO CSRG 13Y 17/16/91 0 l
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- ll AN ALTERNATIVE ULTRASONIC EXAMINATION ll
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Technical Document 901 (O Main Steam Header Alternativo V Examination Qualification March 1,1990
1.0 PURPOSE
This paper portains to the qualification of an attornativo ultrasonic technique that will be employed at both McGuire and Catawba Nuclear Power Stations. The componont is the main steam system. The wold joint of import is tho main steam heador (1) to transition ploco (2) wold (soo figuro # 1), in accordance with Section XI of the American Socloty of Mechanical Enginoors Boller and Pressuro Vossol'Codo (ASME), an attornato oxamination technique may be substituted for techniques specified in the Code, provided that the Authorized Nuclear Inservico inspector Is satisflod that the results are demonstrated to be equivatont er superior to those of the specified method (soo paragraphs 1111100 (d) and IWA 2240 for more detail). ('
2.0 BACKGROUND
inservico examinations are conducted in accordance with the 1980 edition of ASME Section XI, including all addenda through Wintor 1980 at the McGuire Nuclear Station. At the Catawba Nuclear Station, all inservico examinations are conducted in accordance with the the 1980 edition of ASME Socilon XI, including all addenda through Winter 1981. Appondix til, in both editions of abovo mentioned Codos, stipulatos that an ultrasonic examination calibration block, for Class 1 and 2 forritic piping, be of the same nominal diamotor as the piping component to be examined. Due to the unique desl0n of the transition pleco, locating representative material to produce a calibration standard of the same dimensions has not been possible to dato. The transition ploco tapers from a 10" outsido dimension (O.D.),on the main steam heador sido, to 0.0" O.D. on the valvo side. Ninety six wolds are of this configuration (forty olght at each unit). The header side weld's O.D. varios from 11.5" to 12.0". Page 1 of 13
Technical Document 90-1 O Main Steam Hoador Attornativo Examination Qualification March 1,1990 3.0 SUPPOSITIOlt Tho valvo sido of the transition pleco calibration is established with a 9.0" O.D. calibration block. The supposition is that this calibration block will provido a examination sensitivity equivalent or superior to one that would bo obtained from a calibration block designed to the specifications of the Codo. This supposition is based on the following: 3.1 Due to the geometric configuration of the header to transition ploce weld joint, tho examination shall orly be performed from tho transillon side of the wold. 3.2 The thickness of the 9.0" O.D. calibration block and the header sido of the transition ploco are the same. Therefore, the calibration block reflector size and depth location requirements would be the same for a 12.0" O.D. calibration block as are in the 9.0" O.D. block. 3.3 The surface area of the 9.0" O.D. block would tend to reflect more of the sound transmitted from a given transducer than the surface area of a 12.0" O.D. block. This would allow loss sound to reach the reflective-surface of the calibration bock reflectors. This means that more_ gain would be requirod to obtain the same amplitudo from the calibration reflectors in the 9.0" O.D. calibration block than 12.0" block. Therefore a calibration from the 9.0" O.D. block should provido a more sensitive examination. 4.0 QUAllFICATION PROCESS Tho 9.0" O.D. calibration blocks from both the McGuire Nuclear Station (50249) and-Catawba Nuclear Station (50356) were compared to a 12" O.D. calibration block (50252). All the calibration blocks are of the same thickness 'd contain the samo
-Page 2 of 13
I ( . Technical Document 901 Main Steam Header Alternativo Examination Qualification s March 1,1990 QUAT.lFICATION PROCESS (CONT 3 sizo calibration reflectors. The only difference is block 50252 does not have a notch reflector. The samo instrumentation (UT instrument, transducer, and cablo) woro utilized throughout the qualification process. Whhout changing the UT. instrument [ sottings, calibrations woro constructed in accordence with the Babcock and Wilcox ! piping examination proceduro ISI 120, rovlslon 25. Each calibration was documented and any deviations were noted (soo Calibration Shoots 901 A through 901F ). The comparisons wore accomplished using a cortiflod 2.25.MHz, .50" diamotor, transducer (32008) coupled to a 6' microdot cable. The ultrasonic instrument was a Tokyo Kolkl, model SM 100. No thermomotor was used. The comparisons woro performed in a environmentally controlled location. Each of the calibration blocks was , in this environment 24 hours prior to the start of the comparisons and romalnod there i throughout the process. i 5.0 RESULTS; The initial distanco amplitudo correction (DAC) curve was performed on the 9.0" O.D. calibration block 50356 using the sido drilled holes. The I.D. notch was compared to this DAC curve. The notch is use to determine the calibration curve's sensitivity to I.D. surfaco initiated degradation. The DAC curve was 10 Decibels (dB) more sensitivo than the notch at roforenco level. This means that the DAC curve's sensitivity is more than 3 timos greator than the calibration sensitivity obtained from the notch. Without changing the sensitivity of the instrument, a calibration was established from the sido drilled holes in the 12" O.D. block, 50252. The amplitudo obtalnod from those reflectors was loss than 2 dB greater than the referenco lovel of block 50356 (The SM-100 adds and subtracts gain sensitivity in 2 dB !ncromonts). Block 50252 does not havo a notch, so no notch comparison was made. Page 3 of 13 _ . ~
I Technical Document 901 Main Steam Heador Alternativo Examination Qualification March 1,1990 5.0 flESjJt.TS (CONT 1 A calibration was then generated from the other 9.0" O.D. block, 50249. The DAC curve obtained was identical to the one obtained from the 12" O.D. block,50252. It was not possible to measure the difference in sensitivity betwoon those two calibration curvos with the instrument control sottings. A graph of all 3 DAC curvos depicts those results in Fi0uro No. 2. The I.D. notch was then compared to this DAC curvo. The DAC curvo was again 10 dB more sensitivo than the notch at referenco lovel. DAC curvos woro generated on each calibration block in the axial and circumforontial direction. In each caso the calibration obtained from the DAC curve was at least 10 dB greater in sensitivity than tho sensitivity obtained from the notch. G.0 CONCLUSION : Tho 9.0" O.D. calibration block can be used for the examination of both wolds attached to the the transition pleco on main steam at both the Catawba and McGuiro Nuclear Stations. The differenco in examination sensitivity using any of the three blocks was < 2 dB. A 2 dB change is recognized by Code anrf throughout the industry to be an insignificant chango in a calibration sensitivity, in any case, calibration blocks 50356 and 50249 provided an examination sensitivity equal to or greator than that obtalnod from the 12" O.D. calibration block,50252. ' Using a calibration block that has no notch reflector for this comparison did not hinder the results. A DAC calibration obtained from sido drill holes normally results in a more sensitivo calibration than one obtained from a notch, in all casos where a notch was availablo the DAC calibration sensitivity was 10 dB more sensitivo than that obtained from the notch reflectors, f T's b Page 4 of 13
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( . Technical Document 901 Main Steam Hoador Alternativo -! Examination Qualification March 1,1990 j; G.0 CONCLUSION (CONT.): This comparison was performed with a .50 diamotor 2.25 MHz transducer Sinco no other transducers woro demonstrated, this alternativo examination technique shall only bo performed with the transducer frequency and size demonstrated. This comparison shall not be used as a justification-for any other alternative j oxamination techniquo other than tho main steam heador to transition ploco valve wold. : t
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11.0 C1 A LLLa nd_f._R e pal tL anrLRe p l a c e men t s (O As re<4 aired by ASMC Section XI, 1980 Edition, a record of the Class 1 and 2 Repairs and Replacements for wort performed from June 10, 1991 to October 15, 1992 is provided and is included in this section of tht> report. The individual wotL request documents are on i11e at the Catawba Nuclear Station. O O EQA408 Page 1 Revision 0 December 9, 1992
i (O CATAWBA NUCLEAR STATION UNIT 1 EOC G REPAIR / REPLACEMENT LOG ASME SECTION XI-1981
-s Exaininntion Dates: F: urn: 0W10/91 To: 10/15/92 Prepared By: QA Technical Support Transmitted By: MClbb- Date: / 0- 2 t 9 ,1 0
REPAIR / REPLACEMENT LOG ASME SECTION XI 1981 U1EOC6 WR# Class Description 4193 MES B REPLACED SNUBBER 1 R ND 0596 4281 MES B REPLACED LOAD PIN,1 R CF 1567 4918 MES B REPLACED SNUBBER BODY 1-R-ND 0226 4918 MES B REPLACED SNUBBER BODY 1 R ND 0596 13716 NSM B REPLACED PLATE 1 R ND-0332 13716 NSM B REPLACED STRUT, REAR BRACKET , PIPE CLAMP, TUBE STEEL 1 R ND 0331 13730 NSM B REPLACED STRUT & PlPE CLAMP, 1 R CA 1552 82028310 01 B REPLACED TRUNION ASSEMBLY ON S.W.I. FILTER HOUSING 91014154 01 B REPLACED BONNET STUDS VALVE 1SV27A 91014155 01 B REPLACED BONNET STUDS VALVE 1SV28A l 91036863 01 B NV PUMP 1 A (REPLACED MECH, SEALS) l l
~
91036868 01 B VALVE 1NV294 REPLACED BONNET STUD NUTS I 91061495 01 A BROKE AND REMADE BONNET JOINT ON l VALVE 1NI157 i 91061797-01 B VALVE 1NV186A (REPLACED YOKE AND BONNET) i 91079959-01 REPLACED VALVE 1ND-03 OLD SERIAL #TD89405 NEW SERIAL #TD89407 91079977 01 B REPLACED VALVE 1NV-14 92003090-01 B REPLACE VALVE 1NV291,3" CUT-OUT WELDS, 1NV4312,13 (NSM11162) u
REPAIR / REPLACEMENT LOG ASME SECTION XI 1981 U1EOC6 h'd 92010120-01 A REACTOR COLLANT PUMP 1C (REPLACED SEALS) 92014280-01 A REPLACED VALVE 1NC-2 92014280-01 A VALVE 1NC002 (REPLACED) 92014312-01 A REMOVAL / REPLACED REACTOR VESSEL l HEAD (REPLACED RV STUDS) 92014312-01 A REMOVED THREADS - REACTOR VESSEL. FLANGE 92014320 01 A RX THERMO COUPLE ASSEMBLY (REMOVE AND REPLACE 92015141-01 A DISASSEMBLED VALVE 1N171 (NO PRESSURE BOUNDARY PARTS REPLACED) 92015253 01 A DISASSEMBLED VALVE 1N1129 (NO PRESSURE BOUNDARY PARTS REPLACED) 92015254-01 A DISASSEMBLED VALVE 1N1180 (NO PRESSURE BOUNDARY PARTS REPLACED) 92019184-01 A REPLACED STEM ON VALVE 1NC31B 92019185-01 A REPLACED STEM ON VALVE 1NC33A 92019186-01 A REPLACED STEM ON VALVE 1NC35B 92019564-01 B REPLACED ANCHORS, PIPE CLAMP, LEFT
- HAND ROD EYE,1-R-SV-1620 92022273-01 A VALVE 1NC003 (REPLACED) 92022274-01 A DISASSEMBLED VALVE 1NI70 (NO PRESSURE BOUNDARY PARTS REPLACED) 92022459-01 A REPLACED TWO SNUBBER 1-R-NI-1384 92022460-01 B REPLACED SNUBBER,1-R-SM-1578, &
1-R-CF-1519 92032839-01 A DISASSEMBLE AND REASSEMBLE PRIMARY g MANWAY SG1C 1 U
REPAIR / REPLACEMENT LOG ASME SECTION XI 1981 U1EOC6 L 92032851-01 A DISASSEMBLE AND REASSEMBLE PRIMARY MANWAY SG-1B 92032858-01 A DISASSEMBLE AND REASSEMBLE PRIMARY MANWAY SG 1 A 92032858-05 A REPLACED SNUBBER 1-R-NI-1314, REPLACED SNUBBER, LOAD STUD LOCK NUT, EXT PIECE SCREWS,1-R-Ni 1314 92032869-01 A DISASSEMBLED SG ID MANWAY COVER (REMOVE AND REPLACE) 92033968-01 A VALVE 1NC001 (REPLACED) 92046405-01 B VALVE 1CF053 (REPLACED BONNET) 92050396-02 B REPLACED LOAD STUD,1-R-NI-107 92052097-01 B REPLACE VALVE 1NV307,3"-CUT-OUT WELDS, 1NV39-10,11 (VN 3773) O V 92052373 01 B REPLACED SNUBBER 1 R-ND-0391 92052913 01 REPLACED STUDS NUTS,1ND1-MJ1 92054065-01 B REPLACED LOAD BOLT,1-R-SM-1011 92054349-01 B REPLACED PIN IN REAR BRACKET,1-R-CF-1567 92054350-01 B REPLACE SNUBBER 1-R-SM-1565, PlPLACED PIN IN REAR BRACKET,1-R-CF-1567 92055498-01 B VALVE 1NV223 (REPLACED) 92055879-01 A DISASSEMBLE AND REASSEMBLE VALVE 1NC27 92060161-01 A SG ID ACCESS HOLE-MACHINED 92060945 01 A REPLACED VALVE IN1119 NEW SERIAL # TD89439 ITEM # CSR-128 ( 92062213-01 A REPLACED SNUBBER,1-R-NC-1655
l ASME SECTION XI 1981 U1EOC6 92065299 01 A VALVE 1NC32B (NO PRESSURE BOUNDARY PARTS REPLACED) 92072880-01 A DISASSEMBLED REACTOR COOLANT PUMP 1C (NO PRESSURE BOUNDARY PARTS REPLACED) (O O
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